Table of contents

This Conference Proceedings volume contains the written versions of the contributions presented during the International Conference on Nuclear Capacity building, Education, Research and Applications 2019 (i-concern 2019), it took place at the Royal Ambarrukmo Hotel on Yogyakarta, Indonesia from September 6-7, 2019.

The Conference provided a forum for discussion and sharing between lecturers, researchers, academics, practitioners and communities, medical specialist, both from universities, research institutes, industries, the government, and the general public in terms of nuclear technology in the aspect of human resources, applications, technology, policies, and innovation. The conference has been a great opportunity for participants coming from Indonesia, Japan, South Korea, Thailand, Austria, and the USA, to present and discuss topics in their respective research areas.

i-concern 2019 conference included 7 plenary lectures and 18 invited speakers, and also oral and poster presentations to allow as many as possible attendances to present their scientific results on the different fields. The manuscripts which have presented were published in the IoP Conference Series: Journal of Physics under the peer-reviewed process.

We would like to thank all participants, keynote speakers and distinguished guests for their contribution to the conference program and these Proceedings. Many thanks go as well to the Indonesian participants for their support and hospitality, which allowed all foreign participants to feel more at home. Our gratitude goes to Prof. Dr. Anhar Riza Antariksawan (Chairman of National Nuclear Energy Agency, BATAN), Prof. Amirreza Jalilian, Pharm D, PhD (International Atomic Energy Agency representative), Prof. Dr. Dong Soo Lee (President of World Nuclear Medicine and Biology), and Prof. Dr. Philipe Hopke (Clarkson University, USA) for their supports and contributions in the conference programs.

Finally, I would like to thank all sponsors, partners, and colleagues, we can continue our collaboration in developing science, technology and nuclear applications in the upcoming activities.

Thank you,

Edy Giri Rachman Putra, Ph.D

Chairman i-concern 2019

All papers published in this volume of Journal of Physics: Conference Series have been peer reviewed through processes administered by the proceedings Editors. Reviews were conducted by expert referees to the professional and scientific standards expected of a proceedings journal published by IOP Publishing.

Kidney failure is a degenerative disease that has a prevalence of nearly 12 to 15% of the total population in the world. Renal scans are one of many diagnostic means which refers to several examinations using radiopharmaceuticals that evaluate the function and anatomy of the kidneys. Technetium-99m-diethylenetriaminepetaacetic acid ([⁹⁹Tc]Tc-DTPA) is a commonly used radiopharmaceutical for kidney scans. Since the half-life of technetium-99m radioisotope, one component of this radiopharmaceutical, is only about 6.0 hours, so an efficient and effective quality control techniques is a necessity. Up to now, two-systems thin layer chromatography (TLC) is a common method used for radiochemical purity (RCP) test of [^99mTc]Tc-DTPA. Recently one-system TLC has been successfully developed for this purpose. Therefore prior to its application, it is necessary to validate as well to compare this method with an established method (WHO Pharmacopoeia). These methods were two-system used Whatman-1 paper as static phase and methyl ethyl ketone (two-system-A) and 0.9% sodium chloride (two-system-B) as mobile phases and one-system used Whatman-1 paper as static phase and acetone: 0.9% sodium chloride (11:9) as a mobile phase. RCP of [^99mTc]Tc-DTPA was then tested using these methods. The retrieved data were processed and validated with some variables like accuracy, precision, and compared using t-test to see whether the above-mentioned TLC systems show a significant difference or not. The analysis results of RCP test of [^99mTc]Tc-DTPA using two-system method was 99.37± 0.48% while using one-system method was 99.20 ± 0.41%. The percentage accuracy of the data between two methods was 99.83%. The t-stat value for both methods was 0.84 so it can be concluded that the results of measurement using one-system method are not significantly different from two-system method.

Extraction of yttrium from Nd hydroxide concentrate by using Di-(2-ethylhexyl) phosphoric acid (D2EHPA) has been performed. Nd hidroxide concentrate (Nd(OH)₃) is a product of rare earth hydroxide (REOH) pilot plant in the Center for Accelerator Science and Technology, BATAN Yogyakarta, which still contains other rare earth metal elements, such as yttrium (Y). In the extraction process, the aquatic phase is Nd(OH)₃ concentrate containing yttrium in HNO₃ and as extractant or organic phase is D2EHPA in kerosene. The parameters studied were the concentration of HNO₃, the concentration of D2EHPA in kerosene, and stirring time. The result of the optimization process from the research get the following conclusions: the optimum concentration of HNO₃ is 1 M, the concentration of D2EHPA in kerosene is 30%, and the optimum stirring time is 25 minutes. In this condition the Kd of Y = 0.979; extraction efficiency of Y = 93.28%; SF Y-Pr, Y-Nd, and Y-Sm are infinite with SF Y-Gd = 6.080 and SF Y-Dy = 1.395. The results of this study are expected to be used as feed on ion exchange columns to separation and purification of other LTJ elements.

Many people with disabilities who do not get the opportunity to work or the same rights as non-disabled people give encouragement to conduct research to help persons with disabilities. Currently there are several types of research and development on mind wave wheelchairs, but the developed wheelchair has limitations for blind users. Most of the wheelchairs require the user to see the surrounding area in order to move the wheelchair. Therefore, it is not optimal for disabled people who are also visually impaired. To help blind people with disabilities, a wheelchair system with human tracking control capabilities need to be developed. In this study, a prototype of a wheelchair system was developed using Kinect Xbox 360 sensor to read motion data which will then be processed on a mini PC before being sent to an Arduino pro micro based main control to drive the DC motor and track the wheelchair. The prototype has been tested by conducting start and stop maneuver. The results show that the wheelchair prototype has an average success rate for conducting a start maneuver of 87.50% and the average success rate for being able to stop after carrying out a maneuver of 85.83%. In the future the wheelchair is expected to be used by persons with multiple disabilities, namely those who are blind who cannot use an electric wheelchair with mind wave control to help with their daily mobility.

One of the most important factors in health services is the quality and speed of service. However, the speed of service must be supported by the quality of service. Quality is often used as a benchmark and differentiator for a health service. Therefore, all producers and providers of health services must looking for ways to maintain and improve their quality. In this paper quality assurance (QA) and quality control (QC) will be presented at the dose calibrator (DC) to support nuclear medicine services. DC is a very useful tool for measuring radiopharmaceutical activity / dose (which will be given to patients) for diagnostic or therapeutic purposes. For accurate measurements, DC must be calibrated routinely, must pay attention to electronic factors, statistical considerations, ion recombination, background radiation, the source and volume container effects, source position, source adsorption, pure beta transmitter measurements and the presence of contaminants. One of the successes of patient care in nuclear medicine (NM) is by giving accurate doses, according to the type of cancer, the volume and severity of cancer cells. Accurate doses can be achieved by implementing QA and QC at DC, which starts from the calibration stage, checks stability, linearity, and pays attention to parameters that can affect measurement. The aim is to ensure that the measurement results meet the requirements and quality standards set. There are 5 parameters that can support QC implementation, namely PC3M: Person, Chain, Machine, Material and Method. If one of these 5 parameters is missing then QC cannot be implemented.

Safety Analysis of the Irradiation of Tellurium (Te) Target in G.A. Siwabessy Reactor. Providing public service becomes one of the priority programs made by the Head of BATAN, such a program is the radioisotope production of Iodine 131 (I-131), which emits gamma and beta that are utilized for medical purpose. The radioisotope can be produced by irradiating the target of Tellurium dioxide (TeO₂) on the G.A. Siwabessy Reactor core. Tellurium dioxide (TeO₂) is irradiated on the position of Central Irradiation Position (CIP) D-6 and E-7 because the Irradiation Position (IP) is used for Topaz irradiation and CIP (D-6, E-7) is used for the irradiation of Low Enriched Uranium (LEU). Based on the several safety requirements such as analyze the optimum amount of the Tellurium target on CIP (D-6, E-7) with Topaz and LEU. The scope of the research includes the reactivity disturbance, radial power peaking factor and thermohydraulic disturbance. The diffusion group constant of the model uses the program of WIMSD-5B and the result is used for calculating reactivity disturbance and radial power peaking factor with the program package of BATAN-2DIFF. The thermohydraulic disturbance is calculated with using the Generalized Gap Temperature Calculation (GENGTC) program. The calculation of the reactivity of 750 gram (6x125 gram) Tellurium is resulting the change of negative reactivity of-0.27% Δk/k and the value of radial power peaking factor is 1.34 and the temperature at the center of TeO₂ target is 366.7°C and outside the capsule (Aluminum) is 58.39°C, if it is compared to the safety margin of ± 2% Δk/k, PPF_{rad max}=2.6, melting point of Al=660°C, melting point of Te=449.5°C, so all the parameters still meets the safety requirement.

Function test of electron beam extraction for pulse electron. The functional test of pulse electron beam extraction has been performed. The purpose of the functional test is to know the magnitude of the current and the distribution of the extracted electron beam. The plasma current detection system consists of three Rogowski coils mounted on output cables of Ignitor Discharge Power Supply (IDPS), Arc Discharge Power Supply (ADPS) and Faraday Cup (FC), while the voltage and pulse width are observed using an Oscilloscope. From the measurement results obtained that the spot and plasma currents are 11,24 A and 119,65 A. At the extraction voltage of 3 kV obtained the maximum extraction current are 13,1 A and 6,7 A for the position of FC near the ignitor electrode and in the middle of the grid respectively. It can be concluded that the pulsed electron beam can be extracted by the distribution of the beam near the ignitor electrode higher than in the middle position of the grid.

As it is well known, limestone is a type of sedimentary rock that has a function as a reservoir of oil and gas. One of the factors that affect fluid saturation of the reservoir is the distribution of porosity inside the limestone that represents a percentage of the total available space for the oil and gas to fill in. Since hydrogen and carbon have strong attenuation to the thermal neutron, the oil-filled in the porosity can be investigated by the neutron tomography technique. Therefore, neutron tomography can be used to visualize the distribution of the porosity of the limestone. In this work, we report the characterization of the porosity inside the limestone obtained from the oil and petroleum gas institution of Indonesia using the neutron tomography technique. Characterization of the porosity using X-ray tomography technique also has been done in order to compare the results. The results show the neutron tomography technique is useful to visualize and characterize the porosity inside the limestone.

Titanium dioxide (T1O2) is well known as the most active and stable semiconductor as an environmentally friendly photocatalytic material to degrade pollutants in aqueous and gas. In this research, TiO₂ thin film was synthesized on a stainless steel surface using DC sputtering method. To enhance the photocatalytic activity, the TiO₂ thin film was doped with a silver (Ag) also using DC sputtering method. The surface morphology, chemical composition, and crystal structure of the thin film were characterized using scanning electron microscopy –energy dispersive spectroscopy (SEM-EDX) and X-rays diffraction (XRD), respectively. Based on SEM-EDX analysis, it's found that the content of silver (Ag) is 10.5 % weight or 2.56 % at.. This condition was achieved for 2 minutes of deposition time. The photocatalytic activity of TiO₂ and TiO₂-Ag thin film was studied using UV light and sunlight. As a model pollutant, it's used methylene blue. It's found that, if the film exposure using UV light, the absorbance for TiO₂ film is 35.85 % and 64.26 % for TiO₂-Ag thin film. If the film exposure using sunlight, the absorbance for TiO₂ film is 17.5 % and 76.74 % for TiO₂-Ag thin film. It can be concluded that the effect of Ag doping can enhance the photocatalytic activity of the thin film.

The effect of applied strain on the luminosity and divergence of neutron monochromator with fully asymmetric diffraction geometry will be reported. The monochromator used silicon single crystal with 200 x 30 x 4 mm³, which has the parallel face of the crystal to the planes (220). The plain used for this monochromator was (311), which has a 31.5 degree to the (220) face. Fully asymmetric diffraction geometry had been fulfilled with the take-of-angle of the monochromator at 63 degrees. Four lines are bending system used for applying the strain to the crystal, which remote-controlled by computer. The 0, 25, 50, 75, 100, 125, 150, 175, 200 microStrain (uStrain) applied the monochromator crystal respectively. Diffracted neutron from the monochromator was monitored by using a neutron camera for evaluating the luminosity and divergence of the beam. The wavelength of the monochromatized beam was calibrated by using a Nickel rod.

The improvement of Bangka's white pepper quality in term of microbial contamination and physicochemical parameters has been done using gamma irradiation. Pepper samples were irradiated using gamma rays with dose of 2 to 10 kGy, and 0 kGy as unirradiated (control). The Harwell dosimeter was used to determine the absorbed dose. To evaluate the storage effect on the Bangka's white pepper quality, the optimum irradiation dose of 8 kGy was used and peppers were then kept at room temperature (27°C) for 3, 6, 9 and 12 months. The results showed that unirradiated sample was contaminated by bacteria and mold, both of them with concentration of 10³ up to 10⁴, while there was no contamination of yeast, E. coli and Salmonella. The physicochemical properties such as light berries, dark-colored berries, moisture, piperine and essential oil contents were 1.7, 0.7, 11, 5.5 and 2.8 (w/w), respectively. Gamma irradiation with dose of 2, 4, 6, 8 and 10 kGy reduced the number of bacteria to 3.5x10¹, 2.5x10¹, less than 10, less than 10 and 1.5x10¹ cfu/g, respectively. While for mold, irradiation from 2 up to 10 kGy reduce the number of molds to become less than 10 cfu/g. From the dose evaluation, irradiation dose of 8 kGy was selected to evaluate the effect of storage time. It was found that storage time up to 12 months, unirradiated sample still showed contamination of bacteria from 10³ up to 10⁴ cfu/g, while the irradiated pepper showed the contamination less than 10 cfu/g. The effect of storage time on physicochemical properties showed that there is no significant change for both unirradiated and irradiated pepper even after kept for 12 months. Piperine and essential oil contents of unirradiated pepper were 5.45 and 2.4%, respectively. Irradiated pepper showed slightly higher piperine content compared to un-irradiated. It can be concluded that gamma irradiation with a dose of 8 kGy is effective to improve the quality of Bangka's white pepper while maintaining its bioactive substances (piperine and essential oil) and other physicochemical properties as well.

The leaching kinetics of sodium zirconate in hydrochloric acid has been studied. Sodium zirconate was the result of melting zircon sand after separation from sodium silicate. The variables studied were temperature, contact time and the mole ratio of solvent to feed (R). These study aims are to determine the optimum conditions, the reaction rate controller and the reaction rate constant (k) and activation energy (Ea) for the leaching process of sodium zirconate (Na₂ZrO₃).This experiment performed by leaching the sodium zirconate in hydrochloric acid with various temperatures of 50 °C, 70 °C and 90 °C, the mole ratio of solvent to feed of 5, 7 and 9, and various contact time of 10 minutes to 50 minutes. The experimental data were analyzed according to the kinetic models for heterogeneous reaction processes by using shrinking core models. It was found that the leaching of sodium zirconate in hydrochloric acid solution is controlled by chemical reaction with the activation energy was-62.974 kJ/mol. The optimum conditions for the performed experiment in the leaching step were achieved at a temperature of 50 °C, the mol ratio of solvent to feed of 5 and contact time of 50 minutes with the conversion of sodium zirconate was 43.43% and the value of reaction rate constant was 0.0027 min⁻¹.

Indoor radon concentration in Madura Island region, East Java Province, has been mapped and determined. The obtained data is useful for health policies of radon in Indonesia and can be used as internationally baseline data through UNSCEAR, IAEA, and WHO. The mapping process has been done using a grid system of 20 km x 20 km, where on each grid there are 5-10 passive radon detectors using CR-39 installed in the houses for 3 to 4 months. After the exposure time, the detector CR-39 is etched using a 6,25 N NaOH solution at 70 °C in the oven for 7 hours to grow traces of alpha particles from radon. The imprints are read using a microscope with 400x magnification. The number of trace amounts of alpha particles in CR-39 shows the amount of radon concentration in the house. It was found that radon concentrations on Madura Island were in the range of 15.11 ± 1.07 Bq m − 3 to 126.93 ± 8.98 Bq m − 3 with an average of 58.74 ± 4.15 Bq m − 3. Radon concentration data in the house and GPS location were then entered into MapInfo Software v.10.5 for a radon distribution map. This research obtains the Regional Map of radon in Madura Island as a part of the indoor radon map in Indonesia.

A simple radiotracer experiment has been carried out to simulate water flow in a conduit made of PVC plastic with a diameter of 2 in. (50.8 mm). The water was supplied from a water tank with a volume of 500 liters During the experiment flow rate of water in the conduit was maintained constant at a speed of 0.2 m.s−1 by adjusting valve at the farthest end of the conduit. Br-82 isotope solution in a concentration of 1 mCi.ml−1 was injected instantaneously into the conduit. Injected isotope follows the bulk flow of water in the conduit. A scintillation NaI(Tl) radiation detector which was placed on the conduit at a distance of 8 m from injection point captures the radiation energy of injected radiotracer when passing it and generate residence time distribution (RTD) curve which represent isotope particle spent in the conduit. To get meaningful information, a mathematical simulation so-called the axial dispersion model has been developed to evaluate the RTD curve with Peclet number, Pe, as a model parameter. The best fitting of the RTD curve model onto the experimental one was achieved when the Pe is equal to 13. The calculated fitting error was 0.003, very extremely low as expected. This result indicated that the axial dispersion model was able to quantify water flow and simulated Peclet number indicated that convection flow is more dominant compared to the radial flow.

Iodine-131 transfer from radiopharmacy facility to nuclear medicine radioablation isolation room must be carried out by fulfilling the safety and radiation protection rules. One effort is to use a syringe carrier. The purpose of this study was to evaluate the use of a customize carrier syringe for the transfer of Iodine-131 in nuclear medicine. Descriptive study with cross sectional approach on the radiation level of a custom carrier box syringe both surface and 1 m distance. Radioactivity of Iodine-131 used is a multiple of 35 mCi (1,295 GBq) to the maximum radiation level limit. Radiation level measurements were performed on 6 carrier boxes. Radiation level of the ALT 01-03 boxes ⩽ 105 mCi, with Hmax = 0.002176 mSv/transfer, the maximum transfer frequency is 5 times/week, and the maximum capacity is 15 syringes/week. Whereas box AG 01-03 ⩽ 175 mCi with Hmax = 0.02397 mSv/transfer, the maximum transfer frequency is 4 times/week, and the maximum capacity is 20 syringes/week. The customize carrier were evaluated in good condition and can be used to transfer Iodine-131 by considering the maximum capacity of each box.

Drought stress is a factor that affects plant growth and development, both in terms of morphology, anatomy, and physiology. Mutant Oryza sativa L. strain 51 of Cempo Ireng cultivar as the result of gamma-ray irradiation is superior mutant black rice strain which has a faster planting period of 10-20 days than its control and shorter plant height. This study aims to determine the morphological, anatomical, and physiological responses, especially the proline content inside the leaves of mutant black rice strain 51. The study used a completely randomized design (CRD) with the treatment of drought stress using PEG 6000 in Yoshida liquid media. The seedlings were planted for 21 days in untreated media, then treated for 14 days. Observation of morphological characters was carried out by measuring plant height, root length, leaf area, and plant biomass. Observations of anatomical characters were carried out by observing the cross-section of the root. Observation of physiological character was carried out by measuring leaf proline levels. The results showed that drought stress with PEG 6000 inhibited the growth and development of mutant rice strain 51. Drought stress reduces plant height, root length, leaf area, plant biomass and the area of root aerenchyma. Proline leaf content increased significantly at a PEG concentration of 30%. Mutant rice strain 51 showed a tolerant response to drought stress with the significant increased of proline, the increased of root stele diameter and the constant number of metaxylem.

The Centre for Accelerator Science and Technology (PSTA) has developed a subcritical reactor for the molybdenum-99 (⁹⁹Mo) production (SAMOP). This device requires an external neutron source. For experimental purposes, SAMOP is still driven by an external neutron source from a critical reactor, i.e. from the radial beam-port of the Kartini reactor. PSTA is also developing a 13 MeV cyclotron (DECY-13) for the production of fluorine-18 (¹⁸F) which can generate neutron as by-products. This cyclotron has an opportunity to be used as an external neutron source for the SAMOP. In this work, particle transport simulations have been carried out to determine the characteristics of the neutron produced by the DECY-13. The simulation results show that DECY-13 produces an average neutron flux of 2.6347 × 10⁹ particles/cm²s and around 97% of them are the fast neutron. Based on the analysis, it concluded that the DECY 13 could be used as an external neutron source for the SAMOP by the addition of a neutron collimator.

Initialized with design phase in 2015, BATAN developed a gamma irradiator, namely the Iradiator Gamma Merah Putih (IGMP). Located in Puspiptek Serpong, the IGMP finished its construction in 2017. Commissioning test was performed for assuring that the installation is designed, constructed and installed according to the operational requirements. The commissioning test consists of cold and hot commissioning. Cold commissioning refers to testing the operation of the irradiator without radioactive sources. The test was carried out by doing a checklist on the operating table list. The test showed that in all operations, all irradiator equipment and systems are functioning well as per the requirements. It was then concluded that the irradiation facility was ready to receive radioactive sources. In July 2017, the gamma irradiator was loaded with 301 kCi of Cobalt-60 sources provided in 29 source rods distributed into three racks individually controlled by hoist mechanism. Hot commissioning was carried out by lifting up all radioactive sources, and then radiation exposures were measured. In the preliminary tests, there were some locations at the third floor, where the radiation exposures were too high. It was then be minimized by correcting the roof plugs positions and by adding lead material as additional shielding. Finally, measurements show that all radiation exposures were less than 1 μSv/h and safe for public.

Low dose gamma film dosimeter based on chitosan and starch bio-polymer with methyl orange dyes has been synthesized and characterized. The aim of this research was to synthesis radiochromic film dosimeter used biopolymer material such as chitosan and starch with methyl orange dyes as the color indicator and also to investigate the effect of gamma irradiation on film dosimeter response. The film dosimeter was prepared by mixing chitosan and starch at gelatinization temperature then added with methyl orange dyes. Biopolymer solution then casting on the flat glass to produce a thin film with uniform thickness, after that film dosimeter was irradiated at 1, 3, 5, and 9 kGy. To analyze the quantitative response of irradiation, the film dosimeter was characterized by UV-Visible. The result shows that the film dosimeter has changed its color as a response to the irradiation. The higher the dose of gamma irradiation, the higher the net absorbance of it. This research showed that bio-polymer based chitosan and starch is material that has the potential for low dose gamma dosimeter.

The development of the rice cultivation area is needed to increase rice productivity through expanding of marginal land especially in high-elevation areas of Indonesia. Temperature, solar radiation and rainfall influence rice yield by directly affecting the physiological processes involved in grain production. The effects of abiotic stress on grain yield and yield components vary with the growth stage, depending on variety and weather conditions. The major conlinet of rice cultivation in high elevation areas is the lack of cold tolerance varieties. The objective of this research was to obtain the information on the stability of rice genotypes to be adapted in highland across three different high-elevations (700, 900 and 1200 m above sea level). The rice genotypes derived from mutation induction and hybridization treatment were cultivated in the dry season and rainy season. The AMMI analysis revealed KN-10-111, KN-20-124 and RB-10-98 mutant lines were the most stable genotypes across environments evaluated. KK-10-249 mutant line was specific in 900 m above sea level area, C4-30-21, RB-10-95 and KN-20-127 mutant lines adapted in 700 m above sea level area (dry season) whereas B-30-82, IPB117-F-20 and C3-10-171 lines specified in the rainy season. PK-20-133 mutant line had stability in 1200 m above sea level area (rainy season) while OS-30-199 and Sarinah genotypes more stable in the dry season with low temperatures stress conditions. The stable and promising mutant lines could be released and developed a new variety to improve the yield of rice highland adapted.

Silicone patch has active ingredient of radioisotope Phosphorus-32 (³²P) in the form of chromic phosphate (Cr³²PO₄). Radioisotope ³²P is a β− (beta) emitter radionuclide with an energy of 1.71 MeV, having a half-life (T½) 14.3 days. A silicone patch with radioactive content of the radioisotope ³²P has been used for keloid therapy. Radioisotope ³²P as an active substance releases beta emitter continuously which causes the death of fibroblast and inhibits cell proliferation from keloid. In order to provide more optimal results, the distribution of chromic phosphate in silicone patches should be spread evenly. In this case, it provides a good therapeutic effect because of the energy of beta emitter is being released uniform. A chromic phosphate can be made from chromic acid reduction (redox) and phosphoric acid-containing radioisotope ³²P by reducing Chrom VI to Chrom III using sodium sulfite (Na₂SO₃) reducing agent. In this study, we will determine the distribution of radioisotope ³²P in silicone patches using an autoradiography scanner. Data from enumeration results were calculated statistically to obtain a relative standard deviation (RSD). The result shows that silicone patch sample has RSD of 0.036% with an average value of 14009482.6 ± 5041.4DLU (digital light unit) for lane and column size (10 x 14).

Residual radioisotope analysis as a result of cyclotron-based ¹⁸F production is of paramount importance since it relates to the radiation safety of patients as well as radiation workers. In this investigation, 18-MeV proton beams were employed to irradiate enriched water (H₂¹⁸O) target for ¹⁸F production while Talys Evaluated Nuclear Data Library (TENDL) 2017 were used to study the origins of the radionuclide impurities. Gamma rays emmitted by the residual radionuclides were detected using a gamma ray spectroscopic system following a month of decay while their origins were analyzed from the TENDL 2017 nuclear cross-section calculations. Experimental results indicated that several long-lived radionuclides such as ¹⁰⁹Cd, ⁵⁷Co, ⁵⁷Ni, ⁵⁸Co and ⁵⁶Co were recorded by the gamma ray spectroscopic system. The long-lived residual radionuclides were presumably due to proton interactions with Havar window and Silver body. Using the TENDL 2017-calculated nuclear cross-sections, it was discovered that several nuclear reactions responsible for the residual radioisotopes include ¹⁰⁹Ag(p,n)¹⁰⁹Cd which corresponded to the generation of ¹⁰⁹Cd radioisotope, ⁶⁰Ni(p,α)⁵⁷Co and ⁵⁸Ni(p,2p)⁵⁷Co reactions for the formation of ⁵⁷Co, ⁵⁸Ni(p,d)⁵⁷Ni reaction for the production of ⁵⁷Ni radioisotope, ⁵⁸Fe(p,n)⁵⁸Co reaction for the generation of ⁵⁸Co, and ⁵⁶Fe(p,n)⁵⁶Co reaction for the formation of ⁵⁶Co. This experimental result can be used as a reference for future production of ¹⁸F and other radioisotopes should Havar window and silver body are used in the target system.

As a long-lived nuclear waste, iodine (¹²⁹I) which is primarily generated from nuclear fission of uranium or plutonium is considered harmful to human and environment. Therefore, proper steps are required to treat the radioactive isotope. In this work, we propose transmutation of I-129 isotope using cyclotron-based proton bombardment. The TALYS code was employed to calculate nuclear cross-sections of various nuclear reactions possible to transmute I-129 into shortlived radionuclides or stable isotopes. Twelve different nuclear reactions, namely (p,n), (p,2n), (p,3n), (p,np), (p,2np), (p,a), (p,d), (p,2p), (p,nα), (p,γ), (p,³He), and (p,t), which have significant cross-sections (greater than 1 mb) were analyzed. Based on the nuclear reactions, there were 6 possible stable isotopes produced from proton bombardment of ¹²⁹I, such as ¹²⁹Xe, ¹²⁸Xe, ¹²⁷I, ¹²⁶Te, ¹²⁵Te and ¹³⁰Xe. Short-lived radionuclides such as ^29mXe (half life = 8.88 days), ¹²⁷Xe (half life = 36.35 days), ^127mXe (half life = 62.9 seconds), ¹²⁸I (half life = 24.99 minutes), ^125mTe (half life = 57.40 days), ¹²⁷Te (half life = 9.35 hours) and ^127mTe (half life = 106.1 days) could also be possibly produced from the proton irradiation of ¹²⁹I nuclear waste. To sum up, the longest radionuclide could be generated from proton bombardment of ¹²⁹I nuclear waste is ^127mTe (half life = 106.1 days), which is a lot shorter than ¹²⁹I (half life = 1.57x10⁷ years). This theoretical study indicates that transmutation of ¹²⁹I nuclear waste by proton bombardment into short-lived radionuclides is greatly feasible. Current available cyclotrons in Indonesia may be employed to help transmute ¹²⁹I into short-lived radionuclides or stable isotopes. This theoretical study can be used as a reference for future ¹²⁹I nuclear waste if proton beams are employed in the transmutation.

The study was aimed to examine the deoxyribonucleic acid (DNA) damage level between medical and non-medical radiation workers using the comet assay method. The radiation-exposed group (29 subjects) and the control group (29 subjects) were chosen from the administration staff. The assessment of single-strand DNA damage hosted by peripheral blood lymphocyte was performed using the alkaline comet assay, the tail length and long-tailed DNA were measured to detect the DNA damage. An independent sample t-test was used to assess the statistical difference between groups. The results showed that comet tail length mean measured in the exposed worker's group was 25.57±4.4 μm whereas the mean percentage of long-tailed DNA was 6.97±1.53. In the control group, the mean tail length was 23.15±7.57 μm and the long-tailed nucleus percentage was 5.65±1.99. Mean values for the tail length measured were no significantly higher in the exposed group compared to the control group (P=0.15), whereas the percentage of long-tailed nuclei was significantly higher in the exposed group compared to the control group (P=0.007) . The observed single-strand DNA can be measured by using the alkaline comet assay. The DNA damage can be influenced by radiation exposure in medical radiation workers.

The aim of this study is to prepare bio nano-hydroxyapatite based biomaterial for artificial bone using gamma-γ. Preparation of composite hydrogel bio nano-hydroxyapatite based on artificial bone has been carried out via gamma irradiation techniques. The PVA-HAp viscose solutions were prepared using different ratios of HAp (15-30%) with a single PVA solution concentration (20 %) mixed strongly until homogenous. The prepared PVA-HA solution was molded, freeze-thaw to be composites and irradiated using gamma rays (0-20 kGy). The composites were measured its mechanical properties and biodegradation. Surface micrographs of composites were measured using Scanning Electron Microscopy (SEM). The results showed that at optimum conditions (20% PVA-30%,HAp, irradiation dose 20 kGy), the physical appearances of composite more flexible and strong with tensile strength were 1.003 MPa and the elongation at break was 372.33%. With increasing irradiation and HAp content up to 30%, the biodegradation of composite decreased. From SEM measurement the pore sizes of the composite were heterogeneous. PVA-HAp composites prepared using gamma irradiation can be considered as a candidate for biomaterial.

Wound and bacterial infections are often found after periodontal surgery. Collagen has an important role in healing wounds. The purpose of this study is to produce a membrane film which has been antibacterial activity so that it can be developed as a candidate for periodontal wound dressing. Collagen from bovine tendons synthesized with the acidic method to obtain dry collagen. Dry collagen then dissolved to get a 2% collagen concentration and then mixed with ciprofloxacin HCl 0,1% (w/v) and poured on polyacrylic molds. The membrane is then irradiated by gamma rays irradiation at varying doses of 0, 15 and 25 kGy respectively. The irradiated membrane then characterized by its physicochemical properties in the form of functional group analysis, membrane pore size, water absorption, water vapor transmission, tensile strength and percent release of ciprofloxacin HCl. The result of the characterization is that the membranes didn't show any significant changes in the functional group but show any significant changes in size membrane pores, water absorption, water vapor transmission rate, tensile strength, and percent release of ciprofloxacin hydrochloride after gamma rays irradiation.

The process of detecting objects in a path of the image frame is a complex process. Generally, the identification process to find out the condition of a track in the form of objects and the size of objects is done manually by humans, namely using measuring instruments such as rulers, etc. It requires long processing time, and is less efficient, besides that it cannot be done remotely in the form of monitoring on the computer from the camera in terms of measurement. This study aims to create a system of detection and measurement of obstacle on a track using color segmentation method with background subtraction and morphological operation as a result of decision support. This detection and measurement system consists of webcam image acquisition, video extraction, converting frames of RGB to HSV images, color segmentation with background subtraction, gray scaling and thresholding, morphological analysis to improve the results of segmentation, detection and measurement displayed in the form of a Graphical User Interface (GUI). The performance of the system was tested on two background color references in the form of black, namely the asphalt track and white, namely the concrete cement track. The result of testing with the black background, produces an accuracy value of 96%, and with a white background of 100%. The system results in measuring obstacle have an average length of accuracy of 96.16% and a height of 85% on a black background in the form of an asphalt track, and on a white background in the form of cement concrete track results in a length measurement accuracy of 95.99% and a height of 90.88% with the camera moving or fixed.

The terrestrial environment is one of the contributors to natural background radiation. Mamuju Regency, located in the Province of West Sulawesi Indonesia is known as the high natural background radiation (HNBR) area due to its high terrestrial exposure. Botteng Utara Village is one of the areas with dose rates up to 5 mSv/y in Mamuju district. For this reason, measurements were taken to determine the ambient dose received by society. In situ measurements were carried out in Botteng Utara Village using 70 OSL (Type EX-OSLD Environment) installed in 70 houses. The selection of houses is made with various types of building materials, randomly selected from 10 hamlets with each of 7 houses per sub-village. Measurements were done for ± two months from February 20, 2019 to April 12, 2019. The range of ambient dose achieved by measurement was from 51 up to 176 mRem/h. Further investigation using a larger sample number and longer time should be performed to validate this study's results. This result will serve as a baseline for further research regarding the possibility of radiation effects on the society in Botteng Utara Village in Mamuju district.

Sorghum, a local food crop, can be developed on marginal land (drought, salinity, and acidity). Sorghum plant breeding takes a long time to get superior sorghum varieties. Rapid cycling technique is a method of accelerating breeding by repeating the life cycle of plants using immature embryo as planting material. The purpose of this research is to study rapid cycling techniques to accelerate the purification of sorghum mutant lines. In-vitro culture experiments were designed using a Completely Randomized Design (CRD) and Randomized Complete Group Design (RCBD) for in-vivo culture with six treatments of sorghum mutant lines with Super-1 variety as a control and three replications. The results showed that rapid cycling techniques effectively shortened the purification of sorghum mutant lines four weeks faster each generation than conventional methods. The height of GHP-1 mutant line (115.75 cm) is significantly shorter than the Super 1 variety, so it has the potential to be superior food sorghum and high production.

Neutron imaging of lithium-ion coin cell battery was obtained using tomography technique at Neutron Scattering Laboratory in Multi-Purpose Research Reactor G. A. Siwabessy (RSG-GAS) Serpong facility. The coin cell battery was CR2032 (20d x 3.2t mm) type consisted of positive and negative cases made of stainless steel, a cathode layer from lithium Ferro phosphate coated on aluminum foil, polyethylene film as separator, lithium hexafluorophosphate solution in ethylene carbonate and diethyl carbonate as electrolyte, an anode layer from graphite coated on copper foil, and spacer as well as spring made of stainless steel. The neutron tomography was used to observe the inside structure of the full charged coin cell. The observation was carried out with a neutron flux of 10⁷ n/s.cm² at 15 MWatt of reactor power. The image of the object is obtained by a Charge Coupled Detector (CCD) and the reconstruction software based on a filtered back-projection algorithm. The neutron imaging clearly shows the cell structure inside the casing. Even though the cell is not at the center of the casing, but it appears that the cell component consists of a cathode, separator and anode neatly arranged. The cross-cut image shows the important role of spring and spacer in improving the contact between cell and casing. The results showed the ability of neutron tomography techniques at RSG-GAS to investigate in detail the inside structure of a coin battery without disassembly (non-destructive test).

Gamma tomography technique can provide cross-sectional visualization of an object that needed for investigating pipe scale in geothermal power plants. Parallel beam tomography has advantages such as a simple system so that it is easier to apply in the field, but the scanning duration is relatively long. This paper discusses the effect of projections number on the reconstructed images quality and proposes the number of most effective projections for pipe scale investigation. Geothermal pipe sample (OD = 275 mm, t = 10 mm) with scale has been scanned with a parallel beam gamma tomography system. The system consists of a gamma radiation source (137Cs, 80 mCi), scintillation detector, motorized gantry, control module, data acquisition, and computer. The images were reconstructed with six different projections: 128, 64, 32, 16, 8, and 4 projections and the scanning duration: 530.8, 258.9, 127.9, 63.5, 31.7, and 15.8 minutes, respectively. Visually, the 128 projections data produces the smoothest image, whereas 64 and 32 projections images look almost the same. The 16 and 8 projections images are still able to distinguish between the pipe wall, scale, and void even though the 8 projections image looks very blurry. Then, the 4 projections image is not able to visualize the shape of the object. The gaps between the average pipe wall and void gray-scale pixels value of 128, 64, 32, 16, 8 and 8 projections images are 175, 174, 167, 153, 106, and 45, respectively. Based on the scanning duration, visualization, and the gray contrast, then the number of most effective projections is 32.

Oligo chitosan is chitosan with a low molecular weight that derived from the extraction of shrimp shells which are irradiated using gamma radiation. The growth hormone content in oligo chitosan is able to increase the growth and production of crop cultivation on conventional agriculture. The oligo chitosan application is generally sprayed on plants, especially on the leaves and stems of plants. This research aims to find out the most influential method of oligo chitosan application if it's applied to the cultivation of hydroponic floating raft systems, also to explain the effect of the application of oligo chitosan on the growth and production of spinach plants in the cultivation of the hydroponic system. There are three different ways of treatments in this study applying oligo chitosan to floating raft hydroponic system, which are sprayed out on plants (P1), dissolved in hydroponic nutrient solutions (P2), a combination of both (P3), and accompanied by controls. The oligo chitosan concentration given was 100 ppm in each treatment. The method used in this research is a descriptive comparative method, using primary data which is then analyzed quantitatively by using graphs and T-test. The results of this research were the application of oligo chitosan influences the growth and production of spinach plants to the hydroponic floating raft system. The treatment of oligo chitosan dissolution in the hydroponic nutrient solution (P2) was the treatment that gave the best influence to the height of the plant, number of leaves, and the amount of the yield of spinach compared to the other treatments. The width of the leaf does not have a significant effect on each treatment given.

Cell proliferation is a potential biomarker and closely associated with the assessment of general cytotoxicity of chemical and physical agents under study. However, the utilization of these biomarkers in response to environmental stimuli such as natural radiation has not been adequately explored. This research aimed to assess the mitotic index (MI) and nuclear division index (NDI) in lymphocytes as biomarkers for predicting the risks on the health of residents living in high natural radiation area (HNRA) in Salletto and Ahu villages of Mamuju as a studied group. As a control group, people living in another region of Topoyo village were also studied. The observation of these both parameters was done according to the standard protocol as described by the International Atomic Energy Agency (IAEA). The result showed that the percentage of MI of lymphocytes obtained from the studied area was lower compared to those of the control area (6.48 vs. 9.41) whereas the percentage of NDI of lymphocytes obtained from the studied area was higher compared to those of control area (1.59 vs. 1.32). This finding is similar to previous studies in an adjacent area. The NDI obtained from manual counting was much lower than that obtained from the automatic machine for counting (1.59 vs. 22.46), of which it is due mainly to a factor in criteria for counting the cells. MI for the female is lower than that of male and there is a trend of decreasing mitotic index with increasing age in the same group. It is concluded that natural radiation exposure did not affect the proliferation of cells of local people which suggests a low risk of radiation-exposed related to inflammation.

Disused sealed radiation sources (DSRS) that have been stored in the Interim Storage 1 and 2 (IS-1 and IS-2), and High Activity Waste Storage (PSLAT) mainly consist of Co-60, Cs-137and Ra-226. The DSRS is the most suitable to be disposed of in borehole disposal after conditioned and stored. The difficulties faced on storage and disposal are reasoned by long half-life, high gamma-photon radiation, not established disposal system, expensiveness of disposal facility, difficulties on the option to re-export of the DSRS and the activity exceed for near-surface disposal. For that reason, the disposal system for DSRS must be developed with the small scale national facility having some advances as well as costly cheaper, fulfill the safety standard, and could avoid the possibility of human intrusion. The answer to this problem is the borehole disposal concept. By using this concept can be hoped that the problems of DSRS disposal can be handled well, based on DSRS capsule packaged design, site characterization, borehole technology, repository facility, and safety assessment. The selection of borehole disposal technology for DSRS has been made. The selection was made descriptively, involve technological concept and site. One concept of the borehole has been obtained and recommended by the International Atomic Energy Agency (IAEA,) applicable and suitable with the waste and site condition. The concept is Borehole Disposal with unsaturated, very low permeability and high sorption (e.g. clay) host-rock or environments.

Neutron diffraction and the residual stress distribution of magnesium processes by equal channel angular pressing was investigated in term of the grain refinement process. Magnesium is one of the metallic material for a biomedical implant due to the biodegradable properties. The structure and strength of biodegradable metallic material are quite essential to discuss for biomedical implant purposes. The ultrafine-grained structure of magnesium was prepared by equal channel angular pressing until four passes by route Bc at 523 K. The specimen was characterized by electron backscattering diffraction for the structure and neutron diffraction for residual stress. The grain refinement happened during the equal channel angular pressing on magnesium. The texture after four passes of ECAP shows a random orientation compare to coarse grain. The result shows that the strength of the ultrafine grain structure is lower than the coarse grain structure due to the crystal structure of magnesium as hexagonal. The other reason is that the distribution of residual stress on ultrafine grain bulk specimens, which measured by neutron scattering facilities.

River water is very beneficial for households and industries. River functions for households are include drinking, washing, bathing, transportation and tourism. River functions for the industry are electrical energy sources, irrigation, aquaculture, transportation of industrial products and others. Therefore, the characteristics of the Musi River in Palembang, the Kapuas River in Pontianak, and the Kahayan River in Palangkaraya, need to be researched, especially the natural radionuclide content. Water is taken 1 liter each with a plastic container at several sampling locations every 3 km along the river, especially water located near the industry. Samples were taken to the laboratory, allowed to stand for a month, put in Marinelli 1 Liter and measured by gamma spectrometry. The measured radionuclides were Pb-201, Th-230, Th-234, Ra-226, Th-232, Th-228, U-238, K-40 and Cs-137. Radionuclides found in the three river waters are Ra-226, Th-228 and K-40. The concentrations of Ra-226 radionuclide in Palembang, Pontianak and Palangkaraya are 0.06-3.09; 0.02-3.92; and 0.09-4.07 Bq/L respectively. Th-228 concentrations in Palembang, Pontianak and Palangkaraya are 0.03-0.60; 0.05-2.32; and 0.061.09 Bq/L respectively. K-40 concentrations in Palembang, Pontianak and Palangkaraya are 0.19-1.99; 0.19-58.41 and 0.69-1.95 Bq/L. The average concentration of natural radionuclides found in the three river waters is still below the limit value of environmental radioactivity, according to PERKA BAPETEN No. 7 of 2013 namely Ra-226 (1 Bq/L), Th-228 (0.35 Bq/L), Th-232 (0.73 Bq/L), Cs-137 (0.25 Bq/L) and K-40 (1.10⁴ Bq/L).

An experimental 10 MWt power reactor based on high-temperature gas-cooled reactor technology has been planned for Indonesia. The concept was initiated at the end of 2014, and the basic engineering design was completed in 2017. Currently, the development program is focused on detailed engineering design. The type of fuel aimed in the design is a pebble-bed type that contains fuel kernels made of uranium dioxide (UO2) coated in four layers of three isotropic materials. Those layers are a porous buffer layer made of carbon, usually followed by a dense inner layer of pyrolytic carbon (PyC), followed by a ceramic layer of silicon carbide (SiC) to retain fission products, and after that by a dense outer layer of PyC. One of the issues of the fuel system is the problem of corrosion caused by the interaction of fission products such as silver (Ag) and palladium (Pd) with the SiC layer. One of the candidates to resolve the issue is to replace SiC with zirconium carbide (ZrC) which is more resistant to corrosion at high temperatures. In this study, we investigate the effects of the replacement on the neutronic properties of the reactor design at different operating temperatures. For the purpose, we use the SRAC (Standard Reactor Analysis Code) system to calculate the energy spectrum and multiplication factors of the advanced TRISO fuel design. The result of the investigation showed that, in terms of the Doppler coefficient of reactivity, the use of ZrC seems to act more favorably than that of SiC. However, ZrC increases the parasitic neutron capture in the fuel system resulting in lower initial core reactivity which was also confirmed by a slight hardening of the neutron spectrum.

The molecular dynamics simulation using the Morse potential has been applied to calculate the value of self-diffusion coefficients D(T) of some pure metals as Pb, Cr, Ni, and Fe. The simulation then was done using the MOLDY molecular dynamics program. The procedure to calculate these coefficients following several steps: first, determining the Morse potential parameters as ${\mathscr{D}}$, a and r₀; second, simulating the material under consideration using Moldy based on the appropriate ensemble; third, diffusion coefficient calculation using the Green-Kubo method for specific temperature; and fourth, the temperature-dependent diffusion coefficient D(T) based on the Arrhenius. The simulation work has obtained the best results as following: for Pb metal the Morse potential parameter (a = 1.4795 A⁻¹, r₀ = 3.733 Å, and ${\mathscr{D}}=0.2348\text{0.17em}\text{eV}$) with $D(T)=9.68\times {10}^{-9}\text{0.17em}\exp (\frac{-3890.79}{RT})[{\text{m}}^{2}/\text{s}]$; for Cr metal the potential parameters (${\mathscr{D}}=0.3292\text{0.17em}\text{eV}$, a = 1.1005 A⁻¹, and r₀ = 2.2032 Å), with $D(T)=1.73\times {10}^{-3}\text{0.17em}\exp (\frac{-8725.54}{RT})[{\text{m}}^{2}/\text{s}]$; for Ni metal the Morse potential parameter (${\mathscr{D}}=0.3784\text{0.17em}\text{eV}$, a = 1.0649 A⁻¹, r₀ = 2.085 Å), with $D(T)=8.5\times {10}^{-4}\text{0.17em}\exp (\frac{-15794.9}{RT})[{\text{m}}^{2}/\text{s}]$; and for Fe metal the potential parameter (${\mathscr{D}}=0.4174\text{0.17em}\text{eV}$, a = 1.5974 A⁻¹, r₀ = 2.840 Å) with $D(T)=4.22\times {10}^{-7}\text{0.17em}\exp (\frac{-5878.49}{RT})[{\text{m}}^{2}/\text{s}]$. The calculated diffusion coefficients of the work have significant application as for the corrosion study of steels in nuclear reactor design.

Thirteen (13) rivers flowing in the city of Jakarta and Ciliwung is one of them. This river flows through residential, offices, industrial and factories. Activities that exist around the river can cause rivers to become polluted. River sediments act as a potential sink for many hazardous chemicals that can be used as indicators for pollution monitoring of the river. The objective of this study is to assess the heavy metal contamination in the Ciliwung river sediment based on single and combination indices. For the assessment of the Ciliwung sediment quality, measurements of metal concentration in river sediments have been performed. Sampling was carried out at four sampling locations, namely in Kelapa Dua, Kalibata, Condet, and Depok. Analysis of heavy metals in the sample was carried out using instrumental neutron activation analysis method. The analysis result shows that the detected elements in sediment include: Br, Al, As, Ca, Ce, Cr, Co, Cs, Mg, Mn, Na, Sb, Eu, Fe, Hf, K, Sc, Sm, Ta, Tb, Th, Yb, and Zn. The assessment based on the value of the enrichment factor indicates that there has been an increase in the concentration of heavy metals As, Cr, Sb, and Zn in moderate levels due to anthropogenic factors. Based on the geo accumulation index value, it is known that the sampling area is not polluted to moderate contamination. Heavy metals As, Cr, Sb, and Zn in sediments provide a low level of ecological risk to the aquatic environment. Based on the pollution load index value (PLI), all sampling locations are in no pollution conditions. From the evaluation, it can be seen that even for some heavy metals namely As, Cr, Sb, and Zn has been an increase in the concentration value but has not yet reached the polluted level and the ecological risk of heavy metals in the sediments also still provides a low ecological risk.

Safety study of topaz irradiation management at the core rsg-gas position. A study of the management of Topaz stones in the irradiation process in the core position of the Multipurpose reactor G.A Siwabessy in the Batan Serpong (PRSG) has been carried out. A complex process of management because it must meet the technical and administrative requirements of the nuclear power supervisory body (BAPETEN), national and international transportation, and its safety management aspects. From the results of a study of hazard control and risk assessment (HIRADC) a risk rating with rating B is obtained, fulfilling the exposure aspect of container surface according to international transportation requirements (IATA) of <0.4 micro Sv/hour, production requirements as well as fulfilling transportation permits In a predictable safety aspect, a management strategy has been made so that the potential hazards can be overcome, because the results of this study show that Topaz management in in-Core positions with acceptable risk and supervision is required. fulfill administrative requirements, permit the production and be safe for the executor, transportation and environment and fulfill the requirements for re-export.

The utilization of cornstalk as a raw material for bioethanol production is an alternative solution to increase the added value of lignocellulose from agricultural wastes. The glucose content of lignocellulose material can be increased through the hydrolysis process by cellulolytic microorganisms. This research aims to obtain fungi Trichoderma reesei which capable of optimizing glucose content on lignocellulose materials and influence to increase in bioethanol production by Saccharomyces cerevisiae. The experiments were conducted with 2 factorials consist of substrates pre-treatments and hydrolysis. Pre-treatment of substrates by aqua dest (S1), 1% H₂SO₄ (S2) and 1% NaOH (S3) solution. Treatments of hydrolysis consist of control (K) and fungi T.reesei 750 Gray (H). The fungi T.reesei 750 Gray was obtained from optimizing by gamma rays at a dose of 250, 500, 750 and 1000 Gray. The fungi T. reesei 750 Gy have the specific cellulase activity about 0.24 U/mg higher than the fungi T. reesei 0 Gy about 0.16 U/mg. Pre-treatment of substrates with 1% NaOH (1: 5 w/v) solution and hydrolysis by fungi T.reesei 750 Gray (S3H) is suitable for solid fermentation with S.cerevisiae. After 2 days of solid fermentation by Saccharomyces cerevisiae, the bioethanol contents in S3H medium about 387 ppm while S1K (control) about 196 ppm or increase about 98% (ppm/ppm). This result is expected to be an alternative solution for the utilization of cornstalk for bioethanol production.

Evaluation and assessment of 232Th, 226Ra, and 40K as natural radioactivity in surface soil in Pasar Jumat Nuclear Facility (PJNA) are important and are a routine activity to monitor the impact of human activities on changes in the level of natural radioactivity in soils. The monitoring data over 7 years period (2012 – 2018) was evaluated to show the time trends, the ratio concentration, and correlation between the outside of PJNA of natural radioactivity level on surface soils. The average radioactivity trend over 7 years monitoring of 232Th, 226Ra, and 40K concentration have varied data. While the mean ratio of 40K/232Th is range from 0.732 to 2.178. The average level of radioactivity concentration at surface soil during the pre-construction, construction, and operation of the MRT project for 232Th, 226Ra, and 40K are 23.34, 21.64, 21.56 bq/kg, then 19.30, 16.73, 18.93 bq/kg, and 27.47, 26.05, 22.26 bq/kg, respectively. The evaluation result state during the MRT project that only the concentration of 232Th on before construction period has a significantly different the mean. There was no influence of MRT construction on surface soil concentration.

The importance of respiration rates and oxygen saturation (SpO₂) monitoring and the high need for oxygen therapy opens the opportunity for the development of non-invasive respiration rate and oxygen saturation monitoring and controlling system. There are two modes of controlling in this system, automatic and manual mode. In automatic mode, the oxygen flow rate is based on the measurement of the respiration rate using the MLX90614 temperature sensor and tidal volume determination based on the patient's body weight. Oxygen flow control uses a DC motor to open and close the oxygen regulator valve. Oxygen flow will stop when the respiration rate and oxygen saturation level are normal. Oxygen saturation is measured using the MAX30100 sensor. The fabricated regulator control system is capable of flowing oxygen by 5-8 liters per minute using an oxygen mask. The respiration rate measurement was compared with the palpation test, and the deviation was 0.99%. Oxygen saturation reading that used MAX30100 as an oximeter sensor was compared with pulse oximeter fingertip reading, and the deviation was 1.62%. The average flow deviation between the fabricated regulator control system and the calibrated regulator is 2.93%. The result of measuring the response time of the motor for an increase of one liter per minute (LPM) is 1.54 seconds.

in determining the planning of a building foundation there are two things that must be considered in the bottom soil of the foundation, namely the carrying capacity of the permitted soil and the magnitude of the foundation decline. Both of these factors determine the stability of building construction. The stress due to the existence of the building above must be able to be carried by the soil layer under the foundation and must be safe from collapse. In general, the use of pile foundation is used if the subgrade under the building does not have enough bearing capacity to carry the weight of the building and the load above it, and also if the location of the hard ground has sufficient carrying capacity to carry the weight of the building above in a very deep position. At the location of the irradiator it is known from the results of soil testing obtained hard soil at a depth of 30 m so that pile drilling is carried out to that depth. When bore pile casting is carried out it turns out that the required volume of concrete exceeds the planned volume based on BQ (bill of Quantity), so we do the pile wrapping to prevent the mix concrete from flowing out. From the results of several method changes and packaging materials, the results show that the most effective two-layer geotextile wrapper reduces concrete wastage (which functions to carry forward the burden of the building structure above it from the surface of the ground to the layer of hard soil underneath).

Neutron Activation Analysis Techniques more used in determining macro and microcontent in food ingredients. The quality of the test results is needed to produce a valid analysis. To validate the result of the analysis of macro and micro mineral content in food ingredients, quantitative analysis of the elements in the reference standard is NIST SRM 1547 certified Peach Leaves, NIST SRM 1573a Tomato Leaves, and NIST SRM 1570a Spinach Leaves have been done. The Z-score parameter was used as a validation parameter. Elemental with a long half-life was determined quantitatively using the NAA k0 method. The elements were determined quantitatively through long-lived radioisotopes using the k0 Instrumental Neutron Activation Analysis in the G.A Siwabessy reactor. A number of 50 mg-120 mg samples were weighed and irradiated at the neutron flux of 2.5x10¹³ n.cm−2.s−1. Irradiation was carried out for 3 hours on the rabbit system while counting with gamma spectrometry was carried out after cooling time of 23 weeks. Quantitative analysis was carried out using a soft K0-IAEA device. The results of quantitative analysis obtained elements of Ca, Fe, Zn, Rb, Sr on SRM NIST 1547 Peach Leaves; elements of Ca, Cr, Fe, Co on NIST SRM 1573a Tomato leaves and elements Ca, Sc, Zn, Rb, Sr, Co on NIST SRM 1570a Spinach Leaves with uncertainty <10% (3.26-8.68%). The Z-score value ranges from-1.25 to 0.69 and the relative bias ranges from 0.1 to 6.28%, so the results of the analysis of these elements are valid for testing elements in food.

Iodine is an essential element that has an important role in the proper growth and thyroid hormone functioning of humans. Iodine deficiency was correlated with the health status of human-caused by malnutrition. The analytical method to analyze the Iodine content on foodstuffs is limited because Iodine concentration exists in a level of a trace. ¹²⁷I has a ratio of I₀ to s relatively high, and it is possible to obtain ¹²⁸I (t1/2 = 24.5 minutes) using nuclear reaction with an epithermal neutron. Samples were collected at Magelang region, and it consists of foodstuffs that consumed by the citizen. All sample has been dried using Freeze dryer at-90 °C and 0.03 bar for 24-48 hours. After drying, the sample then pounded to get the form of granules smooth, about 100-150 mesh. About 40 to 130 mg of sample was weighed accurately on a clean micro vial of Polyethylene. Irradiation has been carried out at l5 MW reactor power using neutron epithermal for 45 seconds at the rabbit facility of GA. Siwabessy reactor. After cooling 5 to 10 minutes, the irradiated sample then counted for 300 seconds, and the gamma-ray spectra obtained emitted have been analyzed by Hyperlab software. Several standard reference materials of NIST have been used as analytical quality control. The experimental result shows that the Iodine has the Boron ratio, R_B, and the Advantage factor, F_adv, equal to 2.4 and 21, respectively. Trace element of Iodine has been determined quantitatively on nine spices, seven types of meat, and 32 vegetables. The Iodine concentration on spices have average 1.57 ± 0.23 mg/kg with range value 0.38 mg/kg to 3.4 mg/kg. Iodine on vegetable have average of 2.00 ± 0.43 mg/kg with range value of 0.38 mg/kg to 7.30 mg/kg. Meanwhile, its concentration on meat has range 0.71 mg/kg to 2.16 mg/kg, with an average of 1.44 ± 0.28 mg/kg, lower than that on vegetables. Epithermal INAA is a reliable analytical technique for Iodine determination quantitatively.

A study on radiation doses estimation of Argon-41 and Nitrogen-16 airborne released from the Kartini research reactor is already carried out. Kartini reactor is a research reactor with the operating license of 100 KW. Estimation of radiation doses due to the radionuclide released in the airborne from the operating reactor is absolutely needed. This study is performed in order to estimate the internal dose contributions of the Argon-41 and N-16 received by radiation workers as well as the society in the reactor vicinity and to ensure that their dose contributions to the environment are still below the allowable limit value. Argon-41 and Nitrogen-16 are the activation products of gases containing Argon and Oxygen dissolved into primary coolant and released through the ventilation system. The estimated doses were calculated based on the fraction of Ar-41 and N-16 released to the environment through a reactor stack. The discharge rate was calculated by the normal condition for 400 hours of reactor operating in one year. The results showed that the estimated dose for the worker in the reactor building was 0.403 μSv/year, while the society in the reactor building vicinity was 4.45 x 10−3 μSv/year. This value is very small compared to the dose constraint that appointed at Center for Accelerator Science and Technology which is 15 mSv/year for the radiation worker and 0.3 mSv/year for the society surrounding Yogyakarta Nuclear Facility.

The 2017 IAEA Proficiency Test Program has been carried out to improve the performance of the Neutron Activation Analysis (NAA) laboratory. This activity has been organized by the International Atomic Energy Agency (IAEA) cooperated with Wageningen Evaluating programs for Analytical Laboratory (Wepal). Eight samples of ISE (soil samples) and IPE (plant samples) obtained from Wepal under the 2017 Proficiency Test program. Moisture content has been determined using a gravimetric method at 105-110 C and 100-105 for ISE and IPE samples respectively. Target irradiation was carried out for long, medium, and short irradiation using a thermal neutron flux of about 2.3x10¹³ n.cm−2.s−1 at the rabbit facility of GA Siwabessy reactor. Elemental analysis has been done using kay zero (k0) and comparative method of Instrumental Neutron Activation Analysis (INAA). On the kay zero-INAA method, the Al-0.1%Au alloy of IRMM-530R has been used as a flux monitor. Short half-life radionuclide was calculated using an Excel program for the comparative method and correction for a dead and counting time was applied. Quantitative determination has been carried out on a dry weight basis. The water content of the IPE sample was higher than that of the ISE sample. The result of the moister content of the IPE sample was in the range of 8% to 10%; meanwhile the moister content of the ISE sample was 2% to 6%. The elements detected on the IPE samples were less than that on the ISE sample. The elements of Na, Mn, V, Cl, Sc, Fe, Co, Zn, As, Br, Rb, Zr, Sb, Cs, Ba, La, Ce, U, and Th have been determined on ISE sample. In the meantime, for IPE sample, the elements of K, Na, Mn, Cl, Mg, Al, Ca, Cr, Fe, Co, Zn, Br, Rb, Sr, Sb, Cs, La, and Th can be evaluated quantitatively. Most of the elements evaluated have Z-score and Zeta-score of-3 to +3, which indicate good analytical performance for some elements, but for the element, some of them are out layer.

Potassium (K) is an essential nutrient and one of the main minerals in the blood as a counterweight to electrolyte and blood pressure. Decreasing K intake can be one of the causes of increased blood pressure. Mamuju is one area with high hypertension cases. Potassium is widely obtained from foodstuffs. In this study, food was collected from the markets in Mamuju Indonesia and analyzed using neutron activation analysis to determine K concentration. The results for the meat and egg category show that beef has a higher potassium concentration than chicken meat, and Negeri chicken eggs are higher than Kampung chicken eggs. For the vegetable category, six samples have very high concentrations of potassium, namely caisim, kemangi, fern leaves, chinese cabbage, spinach, and beans; and the spices namely turmeric and kencur have high concentrations of potassium. For the fish and seafood category, tilapia has the highest potassium concentration and the lowest shrimp. For staples, the highest concentration of potassium is found in potatoes, the lowest in sticky rice; and the processed soybeans, tempeh has a higher potassium concentration than tofu. Therefore, it is important to pay attention to daily potassium intake by looking at the combination of food and potassium concentration in it, such as by increasing consumption of vegetable foods. On the other hand, high potassium intake needs to be followed by a reduction in sodium and salt intake in food.

Analysis of the TRIGA 2000 core reshuffling scenario based on fuel burn-up and fuel density has been done. One of the requirements of Bandung TRIGA 2000 Reactor reliability is the implementation of maintenance and surveillance activities with predetermined Operation and Limits Conditions (OLC) so that the safety parameters will be met. Core management is one of the maintenance activities carried out. Safety parameters that are required to be fulfilled in the core management include the shutdown margin and the power peaking factors. The scenario carried out in the core management in this analysis that was doing the core compaction by sorting the fuel position on the core based on the fuel burnup and the fuel density. Each core management method was carried out in 4 scenarios. The purpose of this analysis is of course to compare both methods and also to get the optimal scenario to be applied to the core of the existing Bandung TRIGA 2000 Reactor. From the eight proposed scenarios, obtained two scenarios that meet the requirements of shutdown margin and power peaking factor from the OLC, namely scenario 2 with the k-eff value obtained 1.01243, and scenario D with the k-eff value obtained 1.02031. Therefore, scenarios 2 and D will then be proposed as the existing Bandung TRIGA 2000 Reactor core configuration scenario.

The development of radiation utilization, in medical application, increases every year. One of them was the interventional radiology facility. Interventional radiology has been chosen to replace invasive procedures for diagnosing and cure several cases of the blood system. However large radiation exposure for radiation workers remains the main potential of an occupational hazard. Therefore, radiation protection plays an important role in ensuring the occupational dose does not exceed the regulated limits by BAPETEN. The purpose of this study was to determine the estimated effective dose (mSv) received by radiation workers undergoing interventional procedures. Occupational doses were measured using the thermoluminescence dosimeter (TLD) chips which placed on critical organ areas such as thyroid, thorax and gonads / ovaries during interventional procedures. In this study, the interventional procedures carried out for PCI, embolization, PTCA, limb intervention, thoracic intervention and cerebral intervention. The TLD was then read using the TLD Reader 3500 Harshaw. The results of this study showed mean effective dose received by doctors, nurses and radiographers in several hospitals in Indonesia due to carrying out interventional procedures was 0.043 ± 0.034, 0.048 ± 0.064 and 0.047 ± 0.031, respectively. The dose received by the radiation worker is still below the limit regulated by BAPETEN, which is 20 mSv / year. These doses were varied based on the type of interventional procedure and the time of fluoroscopy.

The main structures of the High Temperature Gas-cooled Reactor's core are made of graphite material. High temperature and the high flux of neutron exposure in the HTGR reactor affects the integrity of graphite material. In order to ensure the integrity of the graphite materials, and in-service non-destructive inspection is needed. Commonly, prior to the operation, the radiography technique is conducted to evaluate the graphite material. The aim of this study is to develop a non-destructive inspection method in order to evaluate the quality of graphite materials. Five specimens made from nuclear grade graphite IG-110 produced by Toyo Tanso, Co. Ltd has been radiographically tested using X-ray constant potential machine to evaluate the graphite material. The parameter of the energy and intensity of X-ray has also been used in this computed radiography technique with a white type of phosphor imaging plate. A scanning machine of HD CR 35 NDT with 50 μm laser size and a 300 rpm scan rate equipped with a 16-bit system has been used to result in the digital image of the graphites. The results show that the increase of energy and intensity of the radiation to some extent produces better image contrast. The radiograph of the specimens also shows that there is no defect in the material. According to these results, it could be concluded that the digital radiography technique is appropriate for evaluating graphite material.

Research related to bone fractures is currently focused on accelerating healing time with fewer complications. In some cases related to biological and mechanical factors that interfere with the healing process, it will take a longer time to heal. Hydroxyapatite (HA) is a promising material used as a scaffold for bone implants with various advantages. The in vivo biodistribution of Sc-46 labeled composite (HA-Chitosan-Collagen) remains unclear. In this research, Scandium-46 was prepared as a non-carrier free radioisotope solution by irradiating 100 mg Sc2O3 target in TRIGA 2000 Reactor Bandung. In vivo experiment was performed on Sprague Dawley rats weighing approximately 250 g. Rats bone implant model was divided into two groups with n = 3 per time point. The Sc-46 labeled composite (HA-Chitosan-Collagen) have implanted to rats femur 10 mg with radioactivity 10 μCi. Rats were euthanized using accepted protocol and all organs were counted for radioactivity using Wipe Test Counter with NaI(Tl) detector. The percent of radioactivity measured per gram of tissue weight (%ID/g). Biodistribution results showed that Sc-46 labeled composite (HA-Chitosan-Collagen) using the bone-implant method were significantly different compared with the normal bone for 1, 3, and 8 days of the time interval with p<0.05. These observations suggest that Composite (HA-Chitosan-Collagen) is available for bone implants and remains at the implant site until bone recovery.

In ensuring the correct amount of the absorbed dose received, the proper treatment in dosimeter measurement is needed due to several factors that can affect the measurement results. Therefore, the observation focuses on the measurement results of the absorbed dose of type 3042 AA Harwell fabrication-PMMA dosimeter against storage temperature and post-irradiation time. The dosimeter is irradiated using Gamma Cell Upgrade 220 with a dose rate of 4,718 Gy/hour and a target dose of 10 kGy and 25 kGy. Irradiated dosimeters are treated with storage temperatures at 4°C, 23°C, and 40°C and post-irradiation times at 0 hours, 1 hour, 1 day, 3 days and 7 days. The absorbed-dose measurements are compared with the calibration results of PMMA dosimeter with the Fricke standard. At the target dose of 10 kGy, it shows that the temperature of 23°C has the smallest average error that is 5.76% with a 7-day measurement tolerance time. A similar thing happened at the target dose of 25 kGy, it has the smallest average error of 1.81%. However, the target dose of 25 kGy shows that dosimeter cannot be stored at 40°C longer than 1 day due to error tolerance is reaching 46.09%.

The analytical solution of dee voltage of a cyclotron based on a simple model has been derived. This calculation is needed, since the measurement of dee voltage is difficult to do, because the introduction of measuring device will disturb the impedance of the system. Using such a model, the calculation of dee voltage can be done by solving two coupled and driven differential equations. The derivation is carried using Laplace transformation by neglecting the transient solution of the differential equations. The analytical solution is then compared with the solution obtained using the numerical method, specifically using the fourth order Runge-Kutta method to make sure that the solution is indeed correct. The result can therefore be used to estimate the dee voltage for a given set of parameters. In particular, it will be shown that it is possible to get a high value of dee voltage for a small driving voltage.

High Chromium ODS ferritic steel dispersed by zirconia was synthesized by the Mechanical Alloying process for application as high-temperature nuclear reactor structure material. The zirconia was chosen as dispersoid to increase the oxidation resistance of the steel. The powders of Fe and Cr with composition of Fe-25 wt.% Cr and 0.5 wt.% Zr₂O₃ were processed by milling and isostatic compaction then continued with the sintering process for consolidation. The process of sintering was performed by the plasma-based heating using the new apparatus of APS (Arc Plasma Sintering). The sintering was processed with 40 A current and 22 minutes sintering time to result in the optimal Fe-Cr alloy formation. A microscopy technique with scanning electron microscopy (SEM), and X-ray diffraction (XRD) were applied to analyze the mechanism of the alloying process. The Vickers hardness measurement and the oxidation test were carried out to evaluate the mechanical and high-temperature oxidation behavior. The alloying process was considered by the Fe-Cr interdiffusion with Cr the faster one. The distribution of zirconia observed by SEM-mapping showed the homogeneity distribution in the matrix of the alloy. The Vicker hardness of 142.8 VHN was believed caused by the oxide strengthen and fining the grain. The parabolic oxidation curve obtains from the MSB oxidation test showed good oxidation resistance caused by the formation of the protective layer of Fe₂O₃ and some metastable of ZrO.

The technology of RF ion source for compact neutron generator has been studied. Compact neutron generator is a neutron generator with a relatively small size compared to conventional neutron generator; therefore it is very convenient to be used for field applications. Although the size is relatively small, compact neutron generator has the capability to produce neutrons with high neutron yield and the long operational lifetime which are the requirements of neutron generator for field applications. The main parts of the compact neutron generator are constructed in a small chamber of 2 – 5 cm diameter, 30 – 50 cm length. One of the main parts is ion source to produce positive deuteron ions which will bombard the target to produce fast neutrons. There are some types of an ion source for a compact neutron generator, one of which is radio frequency (RF) ion source. The advantage of the RF ion source is that most of the produced ions (> 80%) are atomic ions. Therefore the efficiency of the ion source is greater and subsequently the neutron yield is greater, small ions beam spot without overheating at the target. RF ion source requires an RF generator/RF power supply. The operating frequency of the RF generator is usually of 13.56 MHz. The output impedance of the RF generator is adjusted to the impedance of the transmission line (50 Ohm). A matching network is used to match the impedance of the RF antenna (0.5 – 2 Ohm) in order to maximize the transfer of RF power and to protect the equipment.

Radiosynovectomy is a therapy performed on patients with acute-level arthritis (rheumatoid arthritis) as an alternative solution besides surgery. Radiosynovectomy is performed using a labeled compound with a particle size of 0.5-10 μm labeled with a β radioisotope. Hydroxyapatite (HA) is a 1-10 μm-sized compound found in bones with the components of Calcium (Ca) & Phosphorus (P). Phosphorus-32 (³²P) is a radioactive form of Phosphorus which emits pure beta rays and is often used for therapy. Labelling HA with 32P tends to be easy to do with a substitution reaction, because phosphorus is the main constituent of HA. Phosphorus-32 was made by irradiating natural sulfur at the Bandung TRIGA 2000 reactor facility following the ³²S (n, p) ³²P reaction mechanism. The separation process of Phosphorus-32 was carried out by a distillation method followed by extraction with 0.01 N HCl accompanied by heating for 30 minutes. The Phosphorus-32 solution is then passed through a 3 gr cation exchange resin. Before Phosphorus-32 was used for Labelling of HA, a Radionuclide Purity test was performed with a gamma-MCA spectrophotometer and a Radiochemical Purity test using paper chromatography. The test results showed Phosphorus-32 had Radionuclide Purity > 99.99% and Radiochemical Purity > 96%. 0.5 mCi Phosphorus-32 which meets the quality test requirements is reacted with 7 mg Ha at pH 7. Then it is vortexed at 1500 rpm for 60 minutes with 70 ° C heating. HA-³²P is separated using centrifugation into residual and supernatant fractions. Measure the radioactivity of both fractions with a dose calibrator. Labeling Yield HA with Phosphorus-32 was obtained 98%. Furthermore this HA is ready to be used in in vivo tests for radiosynovectomy.

The labeled compound ¹³¹I-Hippuran has been known for a long time and was still being used by some hospitals as a medical kit for the study of dynamics kidney function. The application of Labelled compound ¹³¹I-Hippuran begins by intravenous injection to the patients, then monitor the process of biodistribution, secretion, and excretion of Labelled compound ¹³¹I-Hippuran using Renographs. The Bandung TRIGA 2000 reactor has obtained an operating license from BAPETEN in 2017, and has been operating at 800 kW to irradiate various elements including Tellurium to produce radioisotope Iodine-131. Iodine-131 was used as a radioisotope material in Labelled compound ¹³¹I-Hippuran, which was produced to fulfill the requests from An-Nur Hospital, Yogyakarta. Labeled compound ¹³¹I-Hippuran used in hospitals must meet the requirements of Indonesian Pharmacopeia, one of the parameters tested is radiochemical purity. The method used to determine the radiochemical purity is the paper electrophoresis method with phosphate buffer electrolyte pH 9, at a voltage of 300 volts for 1 hour. The radiochemical purity of ¹³¹I-Hippuran using the column chromatography method obtained yield more than 70% with radiochemical purity of 98.81 ± 1.06%. Based on these data, the radiochemical purity of the ¹³¹I-Hippuran kit has met the requirements set by Pharmacopoeia Indonesia V that is >90%.

Gamma Spectroscopy is one of the instruments used in measuring the radioactivity of environmental components. However, an efficiency value from the gamma spectroscopy detector is needed in order to obtain an accurate measurement. Efficiency calibration of the detector can be determined from the calibration curve of the standard source used. The calibration curve of a standard source can be affected by the matrix. The study aims to examine the two of the adjacency matrixes from various standard source for radioactivity analysis of gamma soil samples. The efficiency calibration of standard matrix sand (EG-ML) and ore (IAEA-RGU-1) are y = 3.1761x−0,838 and y = 4.3459x^−0,913 respectively. The qualitative measurement of the radioactivity analysis was not influenced by differences in the two standard sources used, where the analyzed soil samples contained K-40, Bi-212, Pb-212, Bi-214, Pb-214, Ra-226, and Ac-228 which were natural radionuclides. However, the quantitative results of radioactivity values show differences with a percentage of 1.1% to 26.2% respectively. The validation of the method carried out on each EG-ML and IAEA RGU-1 standard source obtained satisfactory results with a bias value of ⩽ 2% is 1.2% and 4.3%, the precision value of ⩽ 8% is 0.6% and 1.4%, and the value of Z ⩽ 2 is 0.32 and 0.03 respectively.

¹³¹I-ortho-iodo-hippuiic acid (¹³¹-Hippuran) labelled compound has been used in nuclear medicine for renal function evaluation. The labelled compound solution administered to patients via intravenous injection. Radiation from the labelled compound tracked by gamma detector in Renograph. PSTNT has succeeded produce ¹³¹-Hippuran to cover the demand from An Nur Urology-Specialized Hospital, Yogyakarta. ¹³¹-Hippuran was purified by column chromatography method. HPLC analysis were performed to specified which fraction has higher radiochemical purity and will be used for patients. ¹³¹-Hippuran stability testing needs to be done related to the decay of radioactive compounds. Three storage temperatures were prepared as follows: 4, 25, and 30^thC. Radiochemical purity of each temperature determined by paper electrophoresis method on day 1, 6, 9, 13, 20, 23, and 30. The static phase used was whatman 1 paper, while mobile phase was phosphate buffer pH 9. The initial radiochemical purity is 99.52%. While on 30" day, radiochemical purity in storage temperatures of 4, 25, and 30°C are 97.04, 96.37, and 96.96% respectively. Statistical analysis using SPSS was performed to determine whether there was a significant difference in the radiochemical purity of each storage temperature. Normality and homogeneity test showed the radiochemical purity is normally distributed and has homogenous variance at three different storage temperature. Furthermore, the result of One-way ANOVA test showed that there was no significant difference of radiochemical purity in various storage temperatures. In conclusion, ¹³¹-Hippuran labelled compound produced by CANST-BATAN Bandung is relatively stable up to 30 days and not affected by storage temperature.

The nature of crystalline materials depends on the individual crystal properties and the features of the polycrystalline state. The direction of crystallite orientation (texture) can undergo evolution during casting, processing, deformation, welding, and also heat treatment. Because texture plays an important role in mechanical characteristics and physical behavior, initial characterization before mechanical treatment needs to be analyzed first. The neutron diffraction method for texture analysis has advantages compared to the x-ray diffraction method, because neutrons can penetrate the material up in the order of centimeters (bulk, texture) compared to x-rays which are only on the surface of the material (surface texture). This research uses magnesium alloy, because this alloy is very light, and is widely used in industries, such as the automotive, computers, communication systems and electronics. The magnesium alloy used is AZ31 type. The AZ31 magnesium alloy is selected due to the most ductile and the most popular amongst AZ wrought alloys (Mg-Al-Zn group). Initial characterization using the neutron diffraction method was held away before the welding procedure was taken out. In this study, a texture neutron diffractometer (DN2), BATAN, set at a wavelength of 1.2799 Angstrom was used to characterize AZ31 material. The neutron source is produced by the GA Siwabessy reactor, which operates at a power of 15 MW. From the characterization of the neutron diffraction pattern, four pole figures {100}, (002}, {101} and {102} were taken. From the pole figure analysis, the crystallite orientation (texture) was obtained in the direction of {001} <110>. The highest intensity lies in the basal center (0002), also seen basal fiber {0001} and prismatic fiber {10-10}

One of the natural radiation that is not realized by humans comes from radionuclides in building materials. So, it becomes necessary to study the natural radioactivity in various building materials to calculate the annual effective dose of the public in Perumnas Bumi Guwosari room model. In this paper, activity concentration of ²²⁶Ra, ²³²Th and ⁴⁰K in 5 cement, 5 sand, 5 red brick, and 5 ceramic samples were bought directly from the local hardware store in Yogyakarta were determined by gamma-ray spectrometry with HPGe detector. The activity concentration of ²²⁶Ra, ²³²Th and ⁴⁰K ranged from 23.87 ± 20.88 to 49.31 ± 31.04 Bq.kg⁻¹, 11.56 ± 12.41 to 36.62 ± 14.34 Bq.kg⁻¹ and 0.1443 ± 11.2029 to 58.82 ± 15.01 Bq.kg⁻¹, respectively in various samples. The radium equivalent activity ranged from 17.7338 to 136.8901 Bq.kg⁻¹ are lower than the limit of 370 Bq.kg⁻¹ set by UNSCEAR. The highest value of external and internal hazard indices was found in ceramic samples 0.3705 and 0.5317 are below the UNSCEAR recommendation (H_ext ⩽ 1 and H_in ⩽ 1). The results of calculating the annual effective dose using RESRAD-BUILD ranged 0.654-0.661 mSv.y⁻¹ is lower than the annual recommended limit of 1 mSv.y⁻¹. The parameters that most influence the increase in external radiation dose rate from building materials are the composition, density, and thickness of the floor and wall.

The use of radiopharmaceuticals for cancer diagnosis and therapy is increasing. The radiopharmaceutical is also used to monitor the progress of a disease and determine the appropriate treatment. However, the use of radiopharmaceuticals needs to pay attention to the alteration in pharmacokinetics, pharmacology, and toxicity that are influenced by the drugs consumed by patients. Interaction between drugs with radiopharmaceuticals will cause alteration in pharmacokinetic effects. Therefore, this study aimed to determine the pharmacokinetic interaction of "-Tc-Glutathione radiopharmaceuticals with doxorubicin cancer drug in mice (Mus musculus). The pharmacokinetic studies were performed using four groups of animal model and each group consists of three rats. The groups were classified to normal mice without treatment of doxorubicin as normal mice control (I), normal mice treated with doxorubicin (II), cancer model mice without treatment of doxorubicin as cancer model mice control (III), and cancer model mice treated with doxorubicin (IV). The radioactivity in blood at a certain interval was then calculated to determine the distribution and elimination half-time. The distribution halftime of group I, II, III, and IV were 0.004±0.001, 0.0037±0.0001, 0.003±0.0001, and 0.0037±0.0001 hours, respectively, while the elimination half-time were 5.310±1.050, 10.7344±0.4692, 72.712±2.427, and 26.9320±7.8152 hours, respectively. The results of the T-test showed that there was a significant difference in elimination half-life of ^99mTc-Glutathione between the treated group and the control group. These results indicate that administration of the doxorubicin before administration of ^99m-Tc-Glutathione needs to be avoided because it can alter the elimination half-life of »-Tc-Glutathione. The results of this study are expected to provide benefits for clinicians in nuclear medicine to avoid the interpretation of incorrect diagnosis results, to achieve high-quality health service and will have a positive impact on the appropriate treatment for patients.

Nowadays, the laboratory at STTN-BATAN prepares and returns components to the storage area manually, where this has the disadvantage of the possibility of making a significant mistake. Therefore, a prototype of a sorting machine is made that can sort electronic components automatically on the conveyor. The sorting machine is made with the 1900 NI-myRIO controller. Components that pass above the conveyor are taken. Images from components will then be processed by means of color pattern matching which will compare the image of the component with the template that has been stored in the program. The object in this study is a resistor component that is above a PCB, with a large resistor that is different. The PCB that has been compared with the template will be passed from the conveyor for a certain time and then driven by a servo motor to the storage area with a separator block. In addition, the type of resistor and the amount will be read and displayed on the user's computer. From the test results, it was found that the accuracy of the sorting machine was 91% with precision being 93%.

Digital Survey Meter model SMD-03 has been made. The Digital Survey Meter model SMD-03 was built using the GM LND-714 as the detector, CD4011 as pulse shaping circuit, ATMEGA 8 as a counter circuit and 8x2 LCD as a display. The purpose of the construction of this digital Survey Meter SMD-03 is to develop nuclear instrumentation, especially digital survey meter, especially in improving the stability counting system. The works principle of GM detector to convert the radiation beam into electric pulses. The electrical pulses are inserted into the inverting circuit and pulse shaping circuit to invert the pulses and formed into digitals pulse. The digitals pulses then are inserted into ATMega 8 to be counted and converted into mR/h and then displayed on the 8x2 LCD, measurement range : 0 – 30 mR/h. This instrument is equipped with a buzzer as a sound indicator, this activity includes the manufacture of hardware and software and testing. From the DC high voltage stability test the value of high voltage instability is 0.1%, and from the test results shows the counting linearity value R² = 1, and counting stability test/chi-square test (X²) = 9.58. The data test results show that the digital survey meter model SMD-03 has been made can function properly.

Kartini research reactor which is located at Yogyakarta Indonesia is intended for research, education and training. Students from universities around the city use the reactor for experiments regularly. Regarding the plan of building the first nuclear power plant in Indonesia, the reactor could be improved as the facility of a nuclear power simulator for personnel training of a nuclear power plant. Some improvements on instrumentation and control system were conducted to support the purpose, such as developments of data acquisition of reactor operation parameters, and internet reactor laboratory for remote experiment through the internet connection. However, a power control system for the automatic operation of the reactor is not developed yet. It is important to design an automatic power control for the improvement of the reactor as a simulator of a light-water nuclear power plant. This paper discusses the design of power control of the Kartini reactor based on the Kartini reactor accident and transient code. The control model refers to that of a light water-cooled nuclear power plant. Calculation results show that the control model is applicable to the Kartini reactor. The criterion of SCRAM actuation of the Kartini reactor is satisfied by a small value (0.1) of a control parameter of b. In the future, the control rod simulator which is available in the Kartini reactor might be used to simulate the control system before it is realized to the real reactor.

The radiolytic reduction method has been used in the synthesis of magnetite, which applied solvated electrons (e,−) as a reductor. The aqueous solution containing iron chloride salt and iso-propanol as scavenger agents were irradiated in the gamma-irradiated chamber at Gamma Irradiator Laboratorium Dr. Mirzan T. Razzak, M.Eng., STTN-BATAN, Indonesia. The purpose of this research is to study the formation of Fe3O4 particles via radiolytic reduction by varying the irradiation dose (25, 50, 75, and 100 kGy). The analysis result using X-Ray Diffractometer (XRD) shows the Fe₃O₄ phases were formed since irradiation dose 25 kGy. As the irradiation dose increase caused the increasing of saturation magnetization of Fe₃O₄ with Ms value 5.24; 8.00; 14.2; 21.1emu/g for irradiation dose 25, 50, 75, 100 kGy respectively. Particle size analysis of Fe₃O₄ that irradiated at 100 kGy has an average size of 331 nm. Functional group identification was confirmed using Fourier Transform Infra-Red (FTIR) Spectrophotometer to show the formation of Fe-O bonds. Based on the characterization results, the radiolytic reduction method has been successfully used in the synthesize of Fe3O4 since radiation dose 25 kGy.

Molybdenum-99 (⁹⁹Mo) is a parent radioisotope of technetium-99m (^99mTc) which is widely used as diagnostic radiopharmaceutical because of its short half-life and ideal gamma-ray energy of 140 keV. Separation of ^99mTc and ⁹⁹Mo is mainly carried out using a radioisotope generator of ⁹⁹Mo / ^99mTc. Alumina column inside the generator has a low absorbency capacity of Mo (20 mg Mo / g alumina). Low alumina capacity requires ⁹⁹Mo with high specific activity in order to minimize the amount of alumina so that the generator size could be kept as small and simple. High specific activity ⁹⁹Mo alternatively can be obtained by Szilard Chalmers's reaction in irradiated molybdenum phthalocyanine (MoPc) target material. The purpose of this study was to optimize the extraction condition of ⁹⁹Mo from irradiated MoPc. The study was conducted with stages consisting of the determination of the number of solvents, the effect of extraction time, and Physico-chemical characterization of 99Mo solution. 5-gram MoPc was irradiated in TRIGA Reactor Bandung for 3 days with 5.10¹² n.s⁻¹.cm⁻² neutron flux. Extraction optimization was carried out using THF, DMSO and NaOH 3M solvents with a ratio of solvent : MoPc (v(ml):w(mg)) were 1: 5, 1:10, 1:25, 1:50, and 1:75. Extraction time was varied for 1, 2, 3, 4, and 5 hours. 3M NaOH with a volume ratio of 1: 5 with an extraction time of 1 hour was considered as an optimum condition to extract ⁹⁹Mo from MoPc. This condition produced an extraction yield of 54.21% and an enrichment factor of 322.53 times with 95% radiochemical purity as (⁹⁹MoO4)^2-.

In this study, we synthesized the adsorbent based zeolite as an adsorbent for toxic metal removal. The modified zeolite adsorbent has been successfully synthesized using polymerization radiation technique by gamma rays. The monomer of acrylamide was applied to be grafted onto zeolite. The irradiation doses used in this study were 10–75 kGy and we obtained the optimum dose for synthesizing the zeolite-g-polyacrylamide by using the simultaneous irradiation technique was 25 kGy, with 99.88% and 48.01% for the gel fraction and degree of grafting, respectively. The zeolite-g-polyacrylamide were characterized by Fourier Transform Infrared Spectroscopy (FTIR), Thermogravimetric Analysis (TGA), Differential Thermal Analysis (DTA) and Scanning Electron Microscope (SEM).

The synthesis and characterization of rare-earth hydroxide as a processed result of monazite sand have been carried out. The synthesis and characterization of rare-earth hydroxide resulting from monazite sand processing are necessary to support the pilot plant activity of rare earth hydroxide produced in the Center of Nuclear Mines Technology BATAN. Rare-earth hydroxide is produced through several stages of the process, namely decomposition of monazite sand with NaOH at 140 °C, partial dissolution with HCl at 80 °C, uranium and thorium deposition, and rare-earth hydroxide deposition with NH₄OH. The rare-earth precipitate was dried in an oven at 110 °C. The rare-earth hydroxide produced is characterized and certified. The rare-earth hydroxide powder is homogenized, then a homogeneous test, stabilization test, and characterization test are conducted. In the evaluation of data obtained the rare earth hydroxide that has been homogeneous, stable, contains the minerals of perovskite (La_0.9Sr_0.1CrO₃), villiaumite (NaF), calcium aluminum silicate (CaAl₂Si₂O₈), bredigite (Ca_13.5B_0.3Mg_1.8Mn_0.4Si₉O₃₂) and cesium sodium uranium chloride (CsNaUCL₆). Certificate of parametric test results in rare-earth hydroxide from 10 laboratories accredited with statistical methods obtained 8 rare earth elements, ie Ce: (27.670 ± 3.004) %, La: (13.846 ± 1.503) %, Nd: (8.447 ± 0.816) %, Y: (1.667 ± 0.140) %, Pr: (6.254 ± 0.286) %, Sm: (1.496 ± 0.330) %, Gd: (0.994 ± 0.211) % and Dy: (0.172 ± 0.005) %. Compared with the rare earth hydroxide product of Myanmar, in the rare earth hydroxide the result from Indonesian monazite sand, Pr content higher, but for Ce, La, Nd contents is lower.

Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung. Plate Type Research Reactor Bandung (PTRRB) core design is one of the result of PTRRB research programs. In the previous study the irradiation facilities at grid E-1 has not been designed and also distribution of thermal, epithermal and fast neutron flux at grid E-1 has not been studied. Since that data is very important especially in radioisotope production and neutron beam tube analysis, therefore in this study irradiation facilities at grid E-1will be designed. Previous PTRRB core design is a base for designing irradiation facilities at grid E-1. Considering geometrical of grid E-1 and aluminum tube dimension there are three possibilities aluminum tube configuration. The configurations are configuration 1, 2 and 3. Each configuration was modelled as arrangement of four aluminum tubes and each tube filled by four aluminum irradiation capsules. That configuration was starting point to made MCNP PTRRB reactor core model so there are three MCNP PTRRB reactor core model. MCNP PTRRB reactor core model is needed because MCNP software are computer program for calculating excess reactivity and neutron flux distribution at grid E-1. Result excess reactivity calculation of three configuration indicate that after installing irradiation tube excess reactivity is lower than of limit excess reactivity value 10.9 % of neutronic safety criteria of PTRRB design. Based on neutronic safety criteria, the three configuration is accepted for irradiation facilities PTRRB. Neutron flux calculation result of three configuration reveals that the highest neutron flux is located at capsule no II and III. Profile of thermal neutron flux, epithermal neutron flux and fast neutron flux of three configurations are similar. Neutron flux of thermal, epithermal and fast neutron of three configuration are slightly different. The calculation result reveal that highest thermal neutron flux at grid E-1 is 2.70 × 10¹³(n/cm².sec) at configuration 2. Based on neutronic safety criteria and thermal neutron flux, configuration 2 is appropriate for irradiation facilities of PTRRB.

Fe is an essential macro element that humans need to carry out their physiological processes. Although many factors that cause stunting cases in Indonesia, Fe anemia in pregnant women, breastfeeding women and infants under two years is believed to be one of the causes of stunting. This study will determine the content of Fe in 73 types of local food from Mamuju Regency, West Sulawesi Province. The information can be useful in preventing stunting, especially stunting caused by iron deficiency. The Fe element is determined using a neutron activation analysis technique that utilizes the G.A. Siwabessy Multipurpose Reactor. The sample irradiation was carried out at a rabbit system that has a thermal neutron flux of about 3.10¹³ n.cm⁻².sec⁻¹. Data acquisition of gamma-ray emitted from target irradiated was performed using gamma-ray spectrometry coupled to the high-resolution detector. Fe concentration in foodstuffs was calculated using the NAA-comparative method. The results showed that green vegetables such as kangkung (Ipomoea Aquatica Forsk), bayam (amaranthus spp), kemangi (ocimum citriodorum), daun pakis (diplazium esculentum), daun katuk (sauropus androgynous), daun seledri (Apium graveolens), daun singkong (cassava leaves), cesim (brassica rapa) and buncis (phaseolus vulgaris) have an elemental content of Fe > 100 mg/kg. Kangkung, bayam, and kemangi are green vegetables that are rich in the element Fe, the concentration of Fe in the vegetables more than 280 mg/kg. Concentrations of Fe minerals in vegetables are higher compared to Fe minerals in beef or other protein sources. The green vegetables are suitable foodstuff to overcome Fe anemia in pregnant women, breastfeeding women and infants under two years.

This research aims to design a stripper positioning system with input in the form of angle values and outputs are the x, y coordinates of each stripper. This system consists of hardware and software. The hardware consists of Fx2424 Super PLC, micro-step driver, stepper motor and dc power supply. The software includes Super PLC programming for stepper motor motion using features of the i-TRILOGI program and LabView program for the user interface. The test results show that stripper A with a length of 85 mm, an input angle of 60 degrees, obtained x; y coordinates are 435; 193mm. For stripper B with a length of 85 mm, an input angle of 240 degrees, obtained x; y coordinates are 400; 118 mm. For stripper C with a length of 85 mm, an input angle of 90 degrees, obtained x; y coordinates are 415; 75 mm. Overall test results show that the stripper position control system can be used to rotate and monitor the position of the stripper on the DEC-13 cyclotron.

A control module for mobile carrier radioactive source has been designed. Mobile carrier radioactive source is a tool used to carry out testing for radiation characteristics both statically and dynamically and to conduct calibration on the Radiation Portal Monitor according to the requirements of SNI IEC 62244-2016. The control module is designed to meet the that requirements, it can set a carrier speed of at least 8 km/h, it can adjust the height of the radioactive source between 1 m and 2.5 m, it has automatic forward and backward direction mode. Furthermore, the mobile carrier can be controlled remotely for personnel tester safety. The control module can stop the mobile carrier suddenly when an emergency occurs. The mobile carrier uses a portable power supply so that it can move freely and easily shifted. To meet these requirements, the driving power of the carrier a motor of 24-volt dc with 250 watts. The radioactive source uses a driving power of 12-volt dc motor with a minimum lift power of 5 kg. The control module designed uses a microcontroller with an android application-based interface that is connected by wireless. In the android application there are virtual numbers and input buttons to give commands to the control module. The application can also receive carrier speed information and the height of the radioactive source. To break the power of driving motor of carrier and the driving power of the lifter of the radioactive source, the mobile carrier uses two-level relays, namely low current conductivity relays and relays with high current conductivity. Next in order to move forward and backward automatically, at each end of the carrier is equipped with a limit switch. The button and top position barriers on the radioactive source lifter use a limit switch.

The present work reports the effect of nitrogen ion implantation on aluminum alloy 7075. The microhardness, corrosion resistance, and surface nanostructure were investigated. The implantation was carried out at energy 60 keV with the ion doses used were 1.70 × 10¹⁷ ion/cm², 1.86 × 10¹⁷ ion/cm², 2.02 × 10¹⁷ ion/cm², 2.17 × 10¹⁷ ion/cm², and 2.33 × 10¹⁷ ion/cm². The microhardness test was performed to study the hardness of the implanted layer which was characterized by X-ray Diffraction (XRD). The potentiodynamic corrosion test was performed in a 0.5 mol/l NaCl solution. The surface nanostructure was investigated by atomic force microscopy (AFM) to study the surface roughness after implantation. The results showed that the microhardness after implantation at 2.17 × 10¹⁷ ion/cm² increased by 90.81%. The increase was attributed to the formation of the AlN phase. The AlN phase was confirmed at 2-theta peaks of 39.53°, 45.84°, 66.90°, and 80.54°. The corrosion test showed the improvement of corrosion resistance by the decrease of corrosion rate from 4.49 mpy to 1.43 mpy. The atomic force microscopy showed the arithmetical mean height (Sa) value was 37.5 nm and the root means square (Sq) value was 47.6 nm. The ion implantation induced the change of material surface due to the penetration of nitrogen ion into the material.

Reflector TRIGA Mark II Bandung waste container shielding using Microshield 7.02 has been conducted. In 1996, TRIGA Mark II power was upgraded from 1MWt into 2MWt, and the reflector was one part of the reactor core that was changed. Reflector waste consists of graphite with activated Co-60. In 2015 the activity was 0.557 Ci with 1,221.5 Kg weight. This large radioactive waste needs to be removed from Bandung Nuclear Area into PTLR-Serpong Nuclear Area. This removal process needs calculations and the basic design of the waste container. Pure lead material is planned to be used for attaining requirements standards of radioactive container category base on Transport Index score. In addition, MicroShield 7.02 is a software that is used for helping to analyze shield thickness and could count exposure rate out of the waste container. This software was also used in this research to calculate the lead thickness and demonstrate the radioactivity in several points. The result of simulation with this software is; lead thickness for the container is 3 cm; the container category is III-Yellow with; Transport Index score is 189 or bigger than 10. With tubular shape with 3 cm thickness it will use 1,945.13 kg pure lead. Then, the dose rate on the surface of the container is 128.6 mSv/hr.

Electroactive materials with excellent performance are developed to be applied in different fields. In this study, Graphene Oxide (GO) was synthesized using the Hummer method then reduced and modified with Cu trough gamma irradiation (radiolytic reduction) for dose variations. The optimum dose that produces the highest electroactive is 35 kGy which was tested with cyclic voltammetry. The results of FTIR analysis show the characteristics of functional groups found in GO and rGO are different. The modification of rGO with Cu was successfully shown from the results of XRD and SEM-EDX analysis. The results of the XRD analysis showed that there are two peaks at position 2 theta 10.58° which showed the presence of GO and at position 2 theta 42.55° which indicates the presence of Cu. The results of the SEM-EDX analysis showed that there is 2.25% wt of Cu on the surface of the rGO.

This Study using Internet of Things to control Radiation Level has been motivated by Trend 4.0 and the nuclear disaster in Fukushima after the unfortunate earthquake and tsunami struck Japan. We want to help radiation protection officer to measure the levels of radiation of the affected zones without compromising the life of the workers. For this reason we have created data from a Temperature sensor is collected by an Arduino board and then transmitted to a smartphone via Bluetooth. The results of experiment the stuff can send measurement data to smartphone via Bluetooth at a range of 0-10 meters. By replacing temperature sensor with a Geiger counter kit we can get radiation control device via smartphone.

Aluminium 5083 is an Al-Mg alloy commonly used in ship hull construction. Although it has good corrosion resistance, this aluminium alloy is susceptible to corrosion in extreme environments for a long time. This research aims is to improve the ability of aluminium 5083 deposited by TiN to increase hardness and corrosion resistance using dc sputtering process. This research was carried out with several processes, namely the study of literature, preparation of tools and materials, manufacturing of test objects, coating process, characterization, data analysis, and report making. Hardness testing was done by Vickers method, corrosion testing was carried out by electrochemical method, and crystal structure test using diffraction X-ray. The results of this study were sputtering time 120 minutes increasing hardness 81.6% or becoming 94.7 VHN. The best corrosion rate at 90 minutes sputtering time is 0.0001 mpy. The formation of the TiN phase in the direction of 111, 200, and 202 planes respectively, was shown through peaks at 2-theta at 36.68°, 42.72° and 61.98°.

To protect operators of equipment using neutron radiation, an alternative material is needed as a neutron shielding which is lightweight and has a high neutron absorption. One alternative material that can be used is wood dust. In this study pure wood sawdust and 30% borax-wood composites were investigated as alternatives to shielding neutrons. Mixing wood sawdust and borax was done using HEM (High Energy Milling) for 1 hour, then pressed at 2000 Psi using a manual press with variations in thickness of 5 mm, 10 mm, 15 mm and 20 mm. SEM characterization results show, the grain size of wood in pure wood and 30% boraxwood composites is still quite large around 50 μm, the EDS results show no significant difference in wood content and 30% borax-wood composites. XRD characterization results showed no new phases were formed in the 30% borax-wood composite. The results of observations with optical microscopy showed that 30% borax-wood composite which were compressed did not form pores but were not evenly distributed. From the compressive test data, there was a decrease in the compressive ability of 30% borax-wood composites compared to pure wood dust from 226.6 N to 110.4 N. The neutron absorption test results using the Neutron Radiography technique with the film technique showed the addition of 30% borax to sawdust increased the neutron absorption rate by an average of 19.05% in wood to 20.24% in 30% borax-wood composites and increased the attenuation coefficient of 0.36 cm· in pure wood to 0.53 cm¹in 30% borax-wood composite.

Chitosan is a polysaccharide from the deacetylation process of chitin, a compound derived from crustacean animal exoskeletons. Chitosan has benefits in various fields, one of them is in health field. Chitosan is known to be able to bind with fat so that it can reduce cholesterol levels in the blood, besides chitosan also has activities as an antibacterial and anticancer. Irradiated chitosan is carried out to degrade chitosan to smaller molecular weight and is easily absorbed to the body. As a new drug, many stages of testing are carried out to determine the mechanism and effectiveness of chitosan compound specifically as an anticancer compound. One of the required data is preclinical study data using animal model. Nuclear techniques offers the results of preclinical study that can identify quickly and accurately the distribution of a drug in the body with the radiotracer principle. Therefore it is necessary to make T-chitosan labeled compounds irradiation (¹³¹I-chitosan-75kGy) and compared with ¹³¹I-chitosan labeled compounds non-radiation (¹³¹I-chitosan) as controls. In this study, the optimum formulation of chitosan and chitosan-75kGy with radioisotope iodine-131 with radiochemical purity > 90% was obtained. Chitosan can be labeled by iodine-131 with the formulation of 150 μL (0.5%) chitosan, 20 μl (5 mg / mL) chloramine T, 20 μl (10 mg / mL) sodium metabisulphite, 10 μL Na^l3I and 5 minutes incubation time at room temperature. While the optimum formulation of chitosan-75kGy labeled is 100 μL (0.5%) chitosan-75kGy, 10 μl (5 mg / mL) chloramine T, 10 μl (10 mg / mL) sodium metabisulphite, 10 μL Na¹³¹I with 1 minute incubation time at room temperature. Radiochemical purity testing was carried out using ascending paper chromatography method with whatman 1 paper as a stationary phase. To separate impurities in the form of I2, chloroform is used as the mobile phase, whereas methanol 90% is used to separate impurities in the form of I−. With this successful in producing labeled chitosan, it is expected that the effectiveness of irradiated chitosan as anticancer compounds can be identified.

Lithium-ion batteries (LIB) as one of the essential rechargeable energy storage for supporting renewable technologies is currently a big issue. It is important to understand the mechanism of lithium-ion batteries in order to improve more durable batteries, long cyclable ability and better efficiency. This work aimed to use in-situ X-ray diffraction (XRD) as a powerful technique for acquiring a fundamental understanding of structure and phase transformations of lithium-ion battery during charge mechanism. The battery consists of LiFePO4 as cathode and graphite as anode material. The results show that some new Bragg peaks occur at 2θ of 39.97° and 47.26°. These indicate a phase transformation occurred from LiFePO4 to FePO4 during the charging mechanism. It can be concluded that in-situ XRD is a powerful tool to understand the phase transformation of lithium-ion batteries during the charging mechanism.

The attenuation coefficient of Neutron shielding made of rubber based has been carried out using neutron radiography and gamma spectrometry facility. The samples were Nytrile Butadiene Rubber (NBR), without and with fillers, Gd (Gadolinium), and B4C (Boron Carbida) each composistion has 5% by weight. Attenuation values obtained from the smallest, as follows, NBR without filler, NBR + 5% by weight Gd and NBR + 5% by weight of B4C. is 2,032, 3,772, 4,359

This research was conducted to assess the concentration of hazardous heavy metals (Cu, Zn, As, Cd, and Cr) in water wells and rivers, around the Adipala Cilacap steam power plant, using neutron activation analysis method. Sample of wells water and river water were taken around the Adipala Cilacap steam power plant. Samples were irradiated with pneumatic facility and Lazy Suzan in the Kartini Research Reactor, at a thermal neutron flux of approximately 0.58x10¹¹ n.cm⁻².det⁻¹. The average concentration of hazardous heavy metals has the smallest metal value of Cr with a value of 0.0006 mg/L and the highest metal Cu with a value of 0.057 mg/L, which is examined in water wells following a decrease in the order of Cu > Zn > As > Cd > Cr. The five hazardous heavy metals under the maximum standard recommended by the WHO/USEPA and Minister of Health's Regulation No. 492. In addition to the hazardous heavy metals, there are 13 other heavy metals that determined its concentration (Al, Ba, Mg, K, Fe, Na, Mn, Ti, La, Ce, Sm, Cs, and V), and obtained the results of the metal concentrations Al exceeds the threshold allowable by Minister of Health's Regulation No. 492 the Year 2010.

The adsorbents based on bacterial cellulose matrices, i.e. bacterial cellulose-co-(poly)acrylamide (BC-PAAM) and bacterial cellulose-co-(poly)acrylic (BC-PAA) has been successfully synthesized using polymerization radiation technique by gamma rays. The irradiation doses used in this study were 25, 50, 75, 100, and 150 kGy, with the dose rate of 5 kGy/h. The results showed that the optimum dose for synthesizing the BC-PAAM by using the simultaneous technique was 50 kGy, with the optimum gel fraction was 90.04 % obtained for mass ratio among acrylamide (AAM) and bacterial cellulose (BC) was 1:4. Meanwhile, the optimum dose for synthesizing the BC-PAA by using the similar technique was 75 kGy, with the optimum gel fraction was 94.27 % for the mass ratio between acrylic (AA) and bacterial cellulose (BC) was 2:3. The Fourier Transform Infrared spectroscopy (FTIR) spectra showed that the AA and AAM had been successfully grafted onto the BC. The increasing of heat resistance of the grafted adsorbent was indicated by Differential Scanning Calorimetry (DSC) analysis.

Initial optimization of fine tuner's position on the cyclotron DECY-13's rf dee system. Initial optimization of fine tuner's position has been carried out on the cyclotron DECY-13's RF dee system. The initial optimization was carried out to obtain the resonance frequency 77,76 MHz between RF generator and RF dee system in accordance with the specification of cyclotron DECY-13. The optimization was performed by measuring cyclotron DECY-13's frequency using the Network Analyzer tool while shifting the fine tuner's position. The shifting of fine tuner's position started from the farthest to the closest gap between fine tuner and dee component with an increment of 5 mm continued with an increment of 1 mm from the nearest measured frequency. We obtain cyclotron DECY-13's frequency for position 0 mm, 5 mm, 10 mm, 15 mm, 20 mm, 25 mm respectively 77,925 MHz, 77,875 MHz, 77,775 MHz, 77,625 MHz, 77,325 MHz, 76,075 MHz and the nearest frequency is 77,75 MHz, obtained in the position of 11 mm from the farthest gap. These results could be used as a reference point in the future experiment mainly in cyclotron's hot test and fine tuner's control system.

Correction of vertical point of projection images using the correct axis tilt parameter in the Octopus software package. In the acquisition process to get a projection image need sample test stability of vertical point directly to the detector. During the acquisition process, the sample test must be still on coordinate and not take a movement. The problem that appears in some tests caused when both of them haven't be done, can make projection image not good. This problem can be handled with the correction parameter and without the repeat acquisition process. The correction of the projection image may concern the vertical point movement of the sample test to the detector. It can decide a conclusion for sample test conditions. Correct axis tilt parameter help to change a better projection image result for the reconstruction process. The first correction was obtained tilt angle amount 0.333289°, the second correction was obtained tilt angel amount-0.463394°, and the third correction was obtained tilt angle amount 0.4903°. The correct axis tilt was succeeded rotate projection image and change the view transaction of reconstruction better and can be read easily.

The Kartini Reactor has been operating safely since March 1979 and has been used for research, education and training. Specifically for education and training, it has been utilized for online reactor physics practicum methods by utilizing the Kartini Reactor. This activity aims to enable students to learn and practice about nuclear reactors with distance learning methods, it adopts from the IAEA program under the name Internet based Reactor Laboratory (IRL). IRL is a physics reactor learning method using the internet that is used in distance learning with the reactor physics experiment guide (Protocol) which is already in regular practice (on site). IRL activities began in 2012 from the results of the reactor workshop at NCSU-America which has operated the IRL, then implemented at the Kartini reactor. IRL was first introduced at the International Youth Nuclear Summit in Jakarta in 2014 and introduced reactor operations to find out the dynamics of the operation of the Kartini reactor in collaboration with Adisutjipto College of Technology (STTA). Then continued collaboration between Center for Accelerator Science and Technology (PSTA) Yogyakarta, Center for Empowerment of Informatics and Nuclear Strategic Area (PPIKSN-BATAN) and Polytechnic Institute of Nuclear Technology (STTN-BATAN). Through the IAEA expert mission in 2017, the IRL system works properly, although limited in three protocols which are reactor operation, power calibration, and fuel temperature reactivity coefficient. The IRL program was last tested for distance learning for FMIPA-UGM students in 2019, it has shown a good performance and we agreed to continue the IRL program as one of the student practicum activities.

Nickel chromium oxide (NiCrO) deposition has been carried out on a glass substrate with a variation of the Argon / oxygen (Ar:O) gas ratio using DC sputtering. The purpose of this study is to determine the effect of the Ar: O gas ratio on the energy gap of the NiCrO layer. NiCrO thin film deposition was carried out using a variation ratio of Argon gas and oxygen 60:40, 70:30, 80:20, and 90:10. To determine the phase formed was analyzed using X-Ray Diffraction (XRD). UV-Vis spectrophotometer test was carried out to determine the transmittance value (% T), then from this data, it can be used to calculate the gap energy. Based on the results of the variation of the gas ratio obtained the largest energy gap of 3.44 eV on the gas ratio variation of 80:20.

Well water is an environmental component that is always used by people but is vulnerable to contaminated. The impact of the contamination of water bodies could cause danger to human health. Water pollution could be caused by radioactivity that exceeds recommended limits. Source of radionuclide pollutants in water bodies could be caused by the operation of nuclear facilities. Analysis of radioactivity has been carried out on several samples of well water near the TRIGA 2000 reactor facility, followed by calculating the internal and external hazard index of radiation dose. The results of the analysis using a gamma spectrometer show that the radionuclides contained in well water samples are not fission products, but they are Ra-226, Bi-214, Pb-214 and K-40 in the form of natural radionuclides. The highest radioactivity in the sample was 5.808 Bq/L from K-40 and the lowest was 0.103 Bq/L from Bi-214. The internal and external hazard index has been determined where the internal hazard index was 0.013-0.023 while the external hazard index was 0.006-0.012 which is below the maximum hazard index value based on UNSCEAR which is ⩽ 1. So, based on the results of this study on the radioactivity parameters show that well water is still safe to be used.

The continuity of the TRIGA 2000 reactor operation is determined by the fuel temperature and the primary cooling water temperature. Currently operating the TRIGA 2000 reactor using 105 fuel configurations it is difficult to reach 1000 kW of power, because the fuel temperature and primary coolant temperature in the core are high. It causes boiling and bubble formation in the reactor core, thus reducing neutron moderation in the core. The results of neutronic calculations on the configuration of 105 fuels in the core at this time, it is known that heat generation is focused into the center of the core, and some fuels have large power fluxes, so that some of these fuels produce high cladding surface temperatures as well and cause boiling. In this research, thermal hydraulic analysis has been carried out using the CFD program package for the configuration of 105 fuels in the core. Based on the results of research on the reactor operated at 500 kW power, the hottest channel is at B5 fuel with the power it generates of 9.43 kW, the maximum surface temperature of the fuel cladding is 126.41 °C, and the temperature of coolant wets 119.92 °C. This temperature has exceeded the saturation temperature of the reactor cooling water 112.4 °C, so that sub-cooled boiling is possible. This situation is in accordance with the conditions that occur in the operation of the TRIGA 2000 reactor, where at 500 kW power has begun to observe bubbles coming out of the reactor core. One effort that can be done to reduce the temperature of the TRIGA 2000 reactor core is to do reshuffling and increase the amount of fuel used.

The determination of radioactivity discharge limits to the atmosphere on Bandung Nuclear Area has been carried out. The purpose is that these values can be used to control the discharge of radioactivity from the TRIGA 2000 reactor stack and the labeled compounds and radiometry laboratory stack in the Area to the atmosphere. The determination method is using PC-CREAM software, assuming the discharge of radioactivity from the stack to the atmosphere occurs under normal conditions and occurs only once. The source terms discussed are radionuclides I-131 and Cs-137, while several the other source terms that were not discussed also contribute to this determination. The initial discharge limits of radioactivity I-131 and Cs-137 from the reactor stack of 4.46E-03 Bq/h and 1.26E+05 Bq/h respectively, while I-131 from the laboratory stack of 2.23E-02 Bq/h. The dose constraint for community members at a distance of 1000 m from the Area is set at 0.15 mSv/y. The parameter needed is source term, reactor building volume, the air flow rate in the reactor stack, stack height, angle and distance between the two stacks, meteorology, topographic roughness, and radionuclide pathway to the community. The result of the calculation obtained the discharge limits of radioactivity for I-131 and Cs-137 from the reactor stack of 7.07E-05 Bq/h and 2.00E+03 Bq/h respectively; and I-131 from the laboratory stack of 3.53E-04 Bq/h.

The rotating table on an industrial gamma-ray CT device is used to rotate the detector consisting of a line scanner and a gamma-ray source around the test object. The process of acquiring the image is done by rotating the detector and the source 360 degrees around the object, and at a certain angle, the object projection image is captured through the line scanner. A stepper motor is used to rotate the rotating table. The rotary motion of the stepper motor is controlled using the Raspberry Pi 3B+ control module which can be accessed remotely using the TCP/IP communication protocol. As an interface to control the motion of the rotating table, a software that is created using the python programming language is used. The gear ratio between the motor and the rotating table is 23 : 161 which takes 7 full rotations on the stepper motor to produce one full rotation on the rotating table. Based on the test results, 25200 pulses input is needed to rotate the rotating table 360 degrees, while one pulse is able to move the rotating table by 0.0143 degrees.

The study of the Thomas Fermi model and its application on the study of the inner crust of neutron star has been done in order to explain pasta phase (the geometric structure changing of atomic nuclei from spherical ones to homogenous liquid) on the transition area from the inner crust to the core of neutron star. The study was carried out by the Wigner Seitz approach on the inner crust that is obtaining the total energy equation as a function of the density of the system, as a Thomas Fermi's model. In this study Thomas Fermi's model explains atomic nuclei that consist of Fermion gas in a system of functional total energy to density by taking into account the contribution of kinetic energy, potential energy and the contribution of interactions between particles. The energy state equation obtained was used to explain the effect of increasing density on the inner crust energy and explain the pasta phase through the interpretation of the graph of Thomas Fermi energy per baryon as a function of baryon density for every geometric structure of atomic nuclei.

To support the operational safety of Soebali 2.0 (Sophisticated electron beam accelerator launched by Indonesia version 2.0), laboratory room condition with clean and dustfree, low temperature and humidity was required, and also maintained its stability using Air Conditioner (AC). In this regard, it was conducted to estimate the calculation of air cooling loads as a reference in determining the technical specification of AC that will be installed in Soebali 2.0 laboratory. Estimation was conducted to determine the air cooling loads that arise related to the construction of the building and supporting equipment for Soebali 2.0, which generates heat as the air cooling loads. Based on the estimation result, the total cooling capacity of the air conditioning system was about 153.585 BTU/hours or 15 kW. It was used for cooling the Soebali 2.0 laboratory room with 900 m³ of volume along with the operational supporting equipment was about 20 °C and relative humidity was 50 %.

Synthesis and characterization of photocatalist TiO₂ doped with Ni for treatment of waste model from nuclear facility. Ni doped TiO₂ as photocatalyst material has been made. Addition of dopant Ni was carried out by impregnation technique. The Ni content was varied between 3, 5, 7 and 10 wt.%. The TiO₂-Ni samples obtained were then characterized by X-Ray Diffractometer and SEM-EDS. The catalyst test is carried out using UV-VIS. The anatase crystal structure appears at 2θ = 25.41°, 37.89°, 48.13°, 55.14° 62.78°. The NiO crystal structure was also found at X-Ray peak 2θ = 38.8°. It obvious that addition of Ni dopants decreased significantly the TiO₂ crystal main size The anatase crystal structure formed on TiO₂-Ni (3 wt.%) is 84.21%. The results of SEM-EDS analysis showed the best success rate of 91.6% wt 3 wt.% Ni addition. The photocatalist material TiO₂-Ni was then applied to treat the standard non-radioactive liquid waste material from BATAN nuclear facility modeled by a mixture based on methylene blue exposed with UV light with variation of time. The degradation rate during processing of methylene blue waste with TiO₂-Ni (3 wt.%) using UV light was measured 0.021/hour. The longer the UV irradiation time is the greater the degradation of methylene blue. The making of TiO₂ photocatalyst by adding variations of Ni dopant has been successfully caried out, with a fairly good success rate. The highest success rate is addition of Ni by 3% with a success rate of 91.6%.

According to WHO, cancer is the second leading cause of death in the world and the seventh cause of death in Indonesia. Currently, cancer sufferers are increasing every year and become a national problem in health. Terbium-161 (¹⁶¹Tb) is a low β⁻-emitter of radiolanthanide (E_β- an average of 0.150 MeV and t_1/2 for 6.9 days) that is potential for cancer therapy as an alternative to ¹⁷⁷Lu which has been widely used in nuclear medicine. Physico-chemical characterization of ¹⁶¹Tb radioisotope in the form of ¹⁶¹TbCl₃ final product solution has been studied including radiochemical purity, radionuclide purity, clarity, acidity (pH), and its stability. Irradiation of the Gd₂O₃ enriched target (98.4% ¹⁶⁰Gd isotope enrichment) was carried out at Bandung TRIGA 2000 reactor for ± 3 days. The separation of ¹⁶¹Tb radionuclide from the Gd/Tb matrix has been done by the extraction chromatography method using two pieces of LN (Eichrom) resin cartridge column. The radiochemical purity of the final product of ¹⁶¹TbCl₃ radioisotope solution was determined using paper chromatography and paper electrophoresis methods. Radionuclide purity of fractions resulted from separation as well as the final products of radioisotope ¹⁶¹TbCl₃ was determined through analysis using a γ-ray spectrometer equipped with a multichannel analyzer (MCA) and HP-Ge detector. The clarity of the solution was determined visually, while the determination of acidity (pH) was carried out using the universal pH indicator paper. In this study, the final product of ¹⁶¹TbCl₃ solution has Physico-chemical characteristics that meet the requirements for nuclear medicine application, namely clear, has a pH of ∼ 1, radiochemical purity of 99.31 ± 0.62%, and radionuclide purity of 99.96 ± 0.03%. The stability of radionuclide purity still meets the requirements (> 99%) for 2 weeks after preparing the final product, but ¹⁶¹TbCl₃ solution with radiochemical purity more than 95% was stable until 3 weeks at room temperature.

A conversion of the TRIGA reactor Bandung has been planned by replacing fuel from rod type to plate type. The fuel replacement causes the fuel arrangement or reactor core configuration should be changed as well as the cooling system. Currently, the reactor cooling system takes place by natural convection with the flow direction from the bottom to the top of the core. The replacement of plate-type fuel with a small distance between plates causes the core cooling process to decrease, therefore to make more effective the forced convection cooling system with the direction of upward flow is required. It is expected that the cooling process will increase. The ability of the cooling system depends on flow distribution in the core at the time of reactor in operating, therefore it is necessary to analyze the distribution of coolant flow and the velocity distribution of the cooling system from the top reactor pool to the reactor core to determine that the coolant flow from the inlet pipe mostly goes to the core. The purpose of this research is to analyze the distribution of coolant flow and flow velocity to the reactor core. The analysis was carried out in a simulation using computational fluid dynamics FLUENT software by creating reactor core modeling. The result shows that the cooling water flows from above along the reactor pool, then the stored energy is reduced so that the flowing slowdown. In this case, resulting in evenly flow distribution to the reactor core.

Crystalline hydroxyapatite (HA) prepared from duck eggshell using the precipitation method. Duck eggshell used because it has higher calcium oxide (CaO) purity than another eggshell. The amount of duck eggshell calcinated to obtain calcium precursor then dropped with phosphoric acid wisely. The hydroxyapatite result modified with a silver (HA-Ag) using gamma radiolysis reduction. Hydroxyapatite powder added with an alcoholic silver ion precursor and followed by high energy gamma irradiation. This modification is to increase the antibacterial activity of hydroxyapatite for further medical applications. The results of the bacterial inhibitory test, showed the largest antibacterial clear zone in 25 kGy irradiation dose of HA-Ag. HA and HA-Ag characterized by FTIR, XRD, SEM and EDX. All characterization result support the forming of pure hydroxyapatite and the presence of a silver particle.

Spinels lithium manganese oxide LiMn₂O_4-δ synthesized from mixtures of different raw materials were used to study the relationship between the synthesis method and properties of the spinel. The investigation was emphasized on phase transition in lithium manganese oxide spinel compound at low temperature studied by means of neutron powder diffraction. It is found that the cubic structure of LiMn₂O_4-δ, synthesized from Li₂CO₃, with space group Fd-3m at room temperature was distorted to orthorhombic symmetry with space group Fddd at 290K and become more obvious down to 10K, where the splitting indicates the structural transition close to tetragonal. The equal proportion of coexisted Mn³⁺ (Jahn-Teller) and Mn⁴⁺ ions is associated with partial charge ordering. It is also found that the sample synthesized from LiOH.H₂O and MnO_x does not show phase transition at low temperatures. The extent of orthorhombic distortion is related to oxygen vacancy, δ, which is affected by the synthesis method such as the choice of starting materials, mixing method and annealing temperature.

This research is motivated by the fact that blood pressure monitoring devices currently available cannot be integrated practically with other electronic health monitoring devices. The research is aimed to obtain a real time-continuous and noninvasive-electronic blood pressure monitoring system with a magnetic coil technique. This technique is a simplified form of the nuclear magnetic resonance (NMR) technique because the induced EMF that is obtained does not involve resonance but rather by sudden population changes and relaxation of the magnetic dipole moments of the proton spin of hydrogen atoms in the blood, both when systole and diastole. The benefit of this research output is that it can obtain noninvasive-electronic blood pressure monitoring devices, and the monitoring process does not interfere with blood flow in the branchial artery samples, so that the monitoring equipment can be integrated with other health monitoring equipment practically. The methodology of this research was carried out by placing a sample arm between two poles of a permanent magnet with a magnitude (7,300±200) gauss and his or her hand inside the receiver coil (involving 2,000 turns), after going through a 500 times voltage gain an induction EMF (in volts) was displayed on digital storage oscilloscope screen. This is done when the sample is relaxed (17 volts is obtained), shortly after jogging (26 volts), and the relaxed state a few moments later (12 volts). The result is that the induced EMF signal enlarges and widens shortly after jogging but slides back when the sample return to relaxed. It was concluded that this blood pressure monitoring equipment of the magnetic-coil technique could be used as a blood pressure monitor.

Neutronic analysis of nuclear reactor systems for ⁹⁹Mo isotope production based on mixed thorium-uranium (Th-U) nitrate fuels has been done. The ⁹⁹Mo isotope is a ^99mTc generator which is the most widely used radioisotope in nuclear medicine. The proposed critical reactor system or critical assembly for ⁹⁹Mo production or CAMOLYP is currently being studied in BATAN Yogyakarta as a continuation of the development of subcritical assembly for ⁹⁹Mo production called SAMOP R&D program. The aim of this research is to obtain the optimum CAMOLYP core configurations, the core is an annular cylindrical provided by the outer ring. The method used is the calculation of the critical level of CAMOLYP for two reactor core configuration models, using the MCNPX computer code. The analysis result shows that there are various configurations of CAMOLYP core to achieve criticality condition. The best configuration of design-A is by using a Th-U nitrate density of 300 g Th-U/L or 120 g U/L, with a volume of 56.7057 L Th-U nitrate, surrounded by 38 TRIGA wt-12% in the outer ring (k_ef = 1.000334). While in Design-B, the best configuration is by using 24 fuel rods with a UN volume of 29.0978 L using the UN density of 300 g U/L (k_ef = 1.0562). The amount of ²³⁵U in the first core design is 3376.74 g, while the second design is 1724.046 g. Based on the total amount of ²³⁵U needed to achieve criticality, the author concluded that the best design for CAMOLYP is Design-B.

DESIGN OF GAMMA IRRADIATOR SIMULATOR CATEGORY IV USING ARDUINO MEGA's. Irradiation technology is increasingly developing in Indonesia. With the increase in irradiator facilities in Indonesia, it is hoped that irradiator control system technology can be applied in the construction and maintenance of irradiator facilities. This study aims to design and test the reliability of motion system irradiator facilities in category IV. The Iradiator Simulator was designed using 5 conveyors and a source motion system, to control the motion system of the iradiator facility, the Arduino Mega 2560 was used. The simulator that was made had dimensions of 550 mm × 650 mm. The simulator test results obtained the reliability coefficient of 0.62, which means that the iradiator simulator made has a high level of reliability.

Austenitic stainless steel 316 has very high mechanical properties and corrosion resistance. This type of steel is widely used both in the nuclear and non-nuclear industries. In the nuclear industry, SS316 is used as a cladding material for uranium fuel due to its good corrosion and mechanical properties, and also low neutron absorption cross-section. In the Center for Nuclear Fuel Technology (PTBBN BATAN), it is used as material for the container of nuclear waste that is to be stored on Temporary Storage Installation of Spent Fuel (KHIPSB3 BATAN). SS316 is used as material for can to contain high-activity solid waste from the testing activity in Radiometallurgy Installation (IRM BATAN). The lid of the container is sealed with the GTAW welding process in order to tightly contain the solid waste. The main problem with the heat treatment and welding process of austenitic stainless steel is the occurrence of sensitization in a temperature range of 500-800°C. Therefore fully electrochemical analysis of SS316 stainless steel in various mediums has been conducted. SS 316 specimen was heat-treated to simulate the heat generated by the welding process. Sensitization analysis was conducted with qualitative and quantitative methods by EIS and EPR, and pitting corrosion resistance was by cyclic polarization method. The solution used for EIS and cyclic polarization test was 0 − 3.5% concentration of NaCl, and for EPR test was a mixture of H₂SO₄ and KSCN. Material characterization before and after corrosion testing was microstructure examination. The result of the corrosion test showed that heat treatment on the temperature range of 500-800°C caused sensitization. The corrosion test curve result showed that a heat treatment temperature of 650°C for 1 hour had the highest activation current. The lowest Rp value for SS316 specimen post heat treatment in 675°C was 69.410 ohm. The welded SS316 specimen had a higher corrosion current than that of the unwelded specimen. The microstructure of the welded specimen showed that there was intergranular corrosion particularly in the HAZ region. The effect of NaCl concentration on the cyclic polarization test showed that the higher the NaCl concentration, the more easily the pitting corrosion. The indication of pitting corrosion occurrence was evaluated by considering the E_pit and E_rp values. The lower E_pit value meant that pitting corrosion was more easily to occur.

Multiband electromagnetic wave absorption have been studied on nanocrystalline (1-x) NiFe₂O₄ (NFO)/(x)BaTiO₃ (BTO) composites. The samples were synthesized by solid state reaction using high energy milling (HEM) instrument. The composite samples were characterized using X-ray Diffractometer (XRD) and vibrating sample magnetometer (VSM) instrument. The X-ray diffraction (XRD) patterns of all the samples show single phase and free from impurities. The NFO sample can be indexed to a single cubic crystal structure with a space group of Fd-3m, No. 227. While, the BTO sample can be indexed to a single tetragonal crystal structure with a space group of P4mm, No. 99. The composite samples consist of two phases, namely NFO and BTO showing soft magnetic performance. The mass magnetization is in the range of 20.0–49.0 emu/g. The electromagnetic parameters of the composites were measured by a vector network analyser in the frequency range of 2 GHz to 18 GHz. The results indicated that (1-x) NiFe₂O₄ / (x) BaTiO₃ composites display three-band electromagnetic wave absorption. The 0.5NiFe₂O₄ / 0.5BaTiO₃ composite displays three-band reflection loss which is larger than the other one and the three-band reflection loss are almost the same, i.e., below the -15 dB. From these experiments it can be concluded that the 0.5NiFe₂O₄ / 0.5BaTiO₃ composite is good candidate for electro-magnetic wave absorption.

In order to enhance the added value of zircon minerals (ZrSiO₄) derived from tailing gold mining in Mandor, Landak, West Kalimantan; the hydrometallurgical process is needed to obtain zirconium products such as zirconium Oxychloride (ZrOCl₂.8H₂O) and zirconia (ZrO₂). Zirconium products that are sold must meet the requirement of Technologically Enhanced Naturally Occurring Radioactive Material (TENORM) or (ThO₂ + U₃O₈) is below 500 ppm. The purpose of this research was to process zircon sand with TENORM content 1784 ppm to be ZrOCl₂.8H₂O and ZrO₂ low TENORM. Zircon sand processing has been carried out through melting zircon sand with NaOH to bind Zr became Na₂ZrO₃ and Si as the impurities to become Na₂SiO₃, water leaching to separate Na₂ZrO₃ from Na₂SiO₃ and other impurities, acid leaching (HCl) to convert Na₂ZrO₃ to be zirconium oxychloride low Si (ZOC-1) then ZOC-1 to be zirconium sulfate base (ZBS), ZBS then being deposited to be ZrO(OH)₂, ZrO(OH)₂ converted to be zirconium oxychloride low TENORM (ZOC-2), ZOC-2 then being crystallized to be ZrOCl₂.8H₂O and calcinated to be zirconia. The results showed that zircon sand from Mandor, Landak, West Kalimantan could be synthesized into ZrOCl₂.8H₂O with NORM 1.2586 ppm and zirconia with NORM = 3.5511 ppm, both products have met the industrial-grade requirement.

Au-Ag nanoalloys have been synthesized using the photochemical reduction method by femtosecond laser from dissolving of potassium gold (III) chloride (KAuCl₄) and silver nitrate (AgNO₃) added into a quartz cuvette in various volume ratios with a total volume of 3 ml. The samples were then called AuxAgy, where x and y were the volume fraction for Au and Ag ions, respectively. The samples were irradiated for 15 minutes of irradiation time and characterized by UV-Vis spectrophotometry to observe the absorption spectra in 300-800 nm range and determine the wavelength at which the Localized Surface Plasmon Resonance (LSPR) peak was observed. The process occurred in a water-only medium, in water medium added with 0.01 wt% polyvinylpyrrolidone (PVP) and in water medium added with 0.1 wt% polyvinylpyrrolidone (PVP). The result showed that LSPR of Au-Ag nanoalloys could be tuned between ∼525 nm for Au and ∼403 nm for Ag in a water-only medium, ∼521 nm for Au and ∼412 for Ag in water medium added with 0.01 wt% PVP and ∼522 nm for Au and ∼419 nm for Ag in water medium added with 0.1 wt% PVP.

The DECY-13 cyclotron is expected to produce a maximum energy of protons beam of 13 MeV. For testing the proton energy, a device for measuring photon energy using a stacked copper foil activation technique is currently being constructed. The activation caused the collision of a proton with copper foils and reactions of ⁶³Cu(p,n)⁶³Zn and ⁶⁵Cu(p,n)⁶⁵Zn have happened. These nuclear reactions produce neutron and gamma radiations; therefore, a study of radiation safety aspects is required to protect the hazard in the experiment of proton energy measurement. The study consists of designing for shielding construction based on radiation safety criteria and mainly determining the thickness of the shielding. The shielding material was portland cement concrete of K500 with a density of 2.3 gr/cm³. By setting a safe maximum dose rate of 50 mSv/year in the position of 350 cm from the neutron radiation source and the proton beam current was taken 1 μA, the required minimum thickness of concrete shielding was 110 cm.

Design of gas flow control in LabVIEW based chemical vapor deposition facilities. To make the TRISO layer in nuclear fuel, argon, acetone, MTS, hydrogen and propelling gas are used. Currently, the regulation of gas flow in fluidized bed chemical vapor deposition facilities is done manually. Coating by adjusting the flow rate of 2 different gas alloys. The system is designed to obtain a proper coating, using Arduino to control the servo motor which regulates the gas valve. The results obtained that the valve can rotate between the range of 0 degrees to 180 degrees, with the addition of 0.5 degrees per step.

Transfer factor of radiocesium from soil to spinach plant (Amaranthus sp). Transfer of Cs radionuclide from andosol soil to spinach plant (Amaranthus sp), which highly consumed by Indonesian people had been studied to obtain the transfer factor value for human internal dose assessment according to soil–crop–human pathway. Spinach plants are planted on andosol soils that have been contaminated with ¹³⁴Cs. The research was carried out by growing spinach plants on andosol type soil media containing ¹³⁴Cs until the plants could be harvested. The number of absorbed and accumulated ¹³⁴Cs by plant parts, namely, the roots, stems, leaves, and flowers, are observed every five days. The amount of ¹³⁴Cs uptake accumulated by plants and ¹³⁴C concentrations remaining in the soil was measured using a gamma spectrometer. Transfer factor values were determined by comparing the concentration of ¹³⁴Cs accumulated by plants to their concentrations in soil media. The results of this study obtained that the transfer factor value at harvest age for consumption, i.e., 52 days was 0.527, and the highest was 6.56 when the plant was 76 days. The transfer factor value of higher than one indicates that the spinach plant is a radiocaesium accumulator.

The morphology structure of super paramagnetic iron nanoparticle (Fe₃O₄/γ-Fe₂O₃) or SPIONs coated by apoferritin was studied to understand the ability of apoferritin in coating iron oxide. The system was synthesized in a solution to approach the human body's physiological condition. Small-angle neutron and x-ray scattering (SANS and SAXS) techniques were conducted to reveal the nanostructure of the nanoparticle. The fractal structure was observed by SANS for the SPIONs itself, with the diameter of the building sphere was 2.8 nm. Meanwhile, the SAXS data suited a model of the polydisperse sphere, which assumed as the existence of coated and non-coated SPIONs apoferritin and free apoferritin itself. Transmission Electron Microscopy (TEM) data confirmed the assumption and concluded that apoferritin unable to cover all the iron oxide.

We developed a single sphere spectrometer (SSS) with a gold foil detector for neutron spectrometry. The detector of SSS is seven gold foil with 11 mm diameter and 0.18 mm thickness, which is placed in the polyethylene sphere of 30 cm diameter. The response of the detector was calculated for neutron in energy range 1×10⁻⁹ MeV up to 1 × 10² MeV using the Monte Carlo method by the MCNPX code system. The calculations were done based on the input of the SSS geometry model, source radiation, and fluence tally models. The validation of this SSS response was done with measure the neutron spectra from ²⁵²Cf standard source at the neutron calibration laboratory of the Center for Technology of Radiation Safety and Metrology, National Nuclear Energy Agency, and compared with Bonner Sphere Spectrometer (BSS) LiI(Eu). Based on this comparison, it was known that the SSS Au foils measurement differs from the BSS LiI(Eu) by about 1%.

X-Ray Diffraction (XRD) profile of pure equal channel angular pressing (ECAP)-annealing nickel samples has been thoroughly investigated for studying the material structures changes that imply to the mechanical behavior. Nickel-based material can be used for several applications such as biomaterial, gear, and some part of the instrument at nuclear facilities, which require high-grade standard material properties. ECAP is one kind of severe plastic deformation (SPD) techniques to obtain excellent mechanical properties without adding another element. However, the ECAP process generates metastable structures due to some mismatch structure and inhomogeneous stress within the material. This problem can usually be resolved by annealing after the ECAP process. In this article, pure Nickel was processed by ECAP at 423 K for two passes. The post-ECAP annealed will be carried out at the temperature range from 298 K until 1373 K. The microhardness test results indicate that the ECAP process increases the microhardness significantly, which remains stable after annealing until 773 K. At higher annealing temperature, the mechanical properties will drop suddenly and reach the microhardness value of pure pre-ECAP Nickel. This behavior could be explained clearly by the XRD data analysis result, which shows similar behavior structure changes. XRD data initially show peak shifting to lower 2θ value, which indicates an expansion to a higher lattice parameter, then at the higher annealing temperature, the diffraction peaks split gradually. This peak splitting could be indexed as pure pre-ECAP Ni peaks, which could be related to the drop of the microhardness value.

Black Rice (Oryza sativa L.) has been developed as a functional foodstuff due to its higher content of anthocyanins and nutrients. Black rice productivity is relatively low, while current drought stress phenomena may decline crop productivity. The breeding effort with gamma-ray irradiation is done to improve the plant's ability to be more tolerant against drought stress and increase productivity. Some researches mentioned the use of gamma-ray radiation could initiate morphological, physiological, and biochemical changes in plants. Nitrate reductase activity can be used as a method of crop yields estimation due to its positive correlation with crop productivity. The study aims to examine the nitrate reductase activity and growth responses of the M5 generation from Cempo Ireng Black Rice strain 13 and 46 results of 60Co gamma-ray irradiation compared to black rice without radiation on drought stress variation. The research was conducted with a completely random design factorial. Drought has become a factor I with 3 levels of spacious capacity (100%, 75%, and 50%). Factor II is the black rice strain (13, 46, and no radiation). The observed variables are growth parameters, nitrate reductase activity, and chlorophyll content. The data obtained were analyzed using ANOVA continued with Duncan test at a significance level of 5%. The results showed that there was a variation of growth, chlorophyll content, and nitrate reductase activities from black rice crops irradiated by gamma rays, which is also showed a different response to drought stress. The black rice strain of 46 is the rice, which more resistant to drought stress evaluated from the growth parameters, the content of chlorophyll, and its nitrate reductase activity is higher than black rice without radiation.

The research was done at the Tissue Culture Laboratory of Center for Application of Isotope and Radiation Technology, Jakarta. Callus derived from shoot tip of garlic cloves was exposed to gamma rays, then cut into sized of 1 mm³ and cultured in Gamborg medium enriched with plant growth regulators (PGRs) depends on the treatment. The PGRs applied are. The experiment was arranged in a randomized factorial design with 2 factors and 3 replications. The first factor was the doses of gamma rays (0, 10 and 20 Gy) and the second factor was different concentrations of PGRs (untreated, 1 and 2 ppm of thidiazuron (TDZ) and Zeatin). The result indicated that the application of 2 ppm TDZ or Zeatin promoted development on irradiated callus at the dose 10 Gy. The highest number of the shoot and the longest shoot were obtained from non-irradiated callus grown on medium enriched with 2 ppm TDZ, followed by 1 and 2 ppm Zeatin, 1 ppm TDZ and without PGRs. Irradiated callus at the dose 10 Gy grown on medium with 2 ppm TDZ was able to form a shoot, while other irradiated callusat the dose 29 Gy were not able to form the shoot.

M5 and M6 of black rice generation that were the product of radiation Cobalt-60 on 300 Gy showed phenotype changed, one of which was the improvement of nutrition content. A polysaccharide is a kind of black rice nutrition from amylose and amylopectin polymers. This research's purpose was to know the amount of starch, amylose, and amylopectin from M5, M6, and non radiated black rice. Content of starch was measured by the Luff Schoorl method, amylose by the Iodine-Colorimetric method, and amylopectin levels were obtained from the difference between starch and amylose content. The results showed that the starch content of M5 and M6 lower than non-radiation, i.e., M5 was 73.77%, M6 was 62.20%, and non-radiated was 83,28%. The amylose in irradiated black rice was 71.08% (M5) and 59,33% (M6), which was lower than non-irradiated (4,85%). Irradiated black rice has lower amylopectin levels than to non-irradiated black rice. Non-radiation black rice was 8.43%, M5 was 2.69%, and M6 was 2.86%.

Experimental and theoretical analysis of heat transfer at Electron Beam Machine (EBM) Laboratory in Center for Accelerator Science and Technology, National Nuclear Energy Agency (BATAN) are required to understand the heat transfer phenomena. The BATAN's EBM is a typical 300 kV/20 mA. The room where EBM is based has to be set up according to the laboratory standard to perform at an optimum level. This work aims to evaluate if the installed two air conditioners with a total cooling capacity 160,000 Btu/hr inside the laboratory are sufficient to reach a temperature of 20 °C and atmospheric relative humidity (RH) from 45% to 55%. The laboratory was stacked up with brick, tinted glass window, aluminum door, and rolling door with a total volume of 836 m³. The experiment was performed in cloudy weather for six days from 8:00 a.m. to 4:00 p.m. and the data of temperatures at each spot were taken every one hour. There were three conditions of this experiment, air conditioner running with laboratory lamps set to be off, air conditioner running with laboratory lamps set to be on, and air conditioner running with laboratory lamps set to be on and insulating 10.5 m² rolling door with 50 mm Styrofoam respectively every two days. The result showed that for the first condition, the average temperature of laboratory and atmospheric relative humidity (RH) was 22.5 °C and 59%, respectively. In the second condition, the average temperature of laboratory and atmospheric relative humidity (RH) was 21.9 °C and 65% respectively, whereas, in the third condition, the average temperature of laboratory and atmospheric relative humidity (RH) were 19.9 °C and 49% respectively. This result indicates that adding thermal insulation such as Styrofoam inside the building helps the air conditioners to reach its targeted temperature and RH.

DECY-13 cyclotron is a radioisotope production cyclotron developed by PSTA. In a cyclotron, it is important to understand magnetic fields and electric field distribution for the proton beam trajectories. This paper describes the distribution of the magnetic field from the experimental measurement. Magnetic field has been converted into 3-dimensional data by extrapolation. Data validation was done by comparing the Opera3D simulation and used in simulations of the beam trajectories. Simulations were carried out by using Scilab 5.4.1 and the Runge-Kutta (RK4) approximation method. The parameters used in DECY-13 cyclotron were 40 kV Dee voltage with a radiofrequency (RF) 77.66 MHz and a fourth-harmonics type. The calculations and simulations result showed the beam could pass through the puller at the distance of the ion source with a puller was 6 mm and the optimum distance of 4 mm. The largest difference in error at z = 6 mm was 0.023 T of the average magnetic field 1.275 T. The phase acceptance in horizontal and vertical motion in the central region was about 38 Degrees from -19° to 19°. This experimental and simulation data could be used as a reference for DeCY-13 cyclotron magnetic and electric field distribution profiles.

Iodine in food usually presents in low-level concentration, so it is not easy for measurement by thermal NAA related to the high background of the Compton. Therefore, the aim of this work is to develop the iodine analysis method in a food matrix, so that the iodine analysis method is obtained, which is guaranteed the validity. In this activity, a number of 50 mg of SRM NIST 1548a Typical Diet, IPE sample and standard were irradiated in a pneumatic system facility at TRIGA 2000 reactor with the power of 700 KW by covering sample using cadmium plates to absorb thermal neutrons. The results of the iodine-128 spectrum analysis at 442.3 Kev in the GENIE 2000 software showed a good prospect for iodine detection, with a limit of detection (LOD) is 0.19 mg/kg. The results of the validation method by accuracy and precision testing stated with % Recovery and RSDr each ranged between 93.6-103.1% and 16.33-16.60, respectively. This data have good agreement with accuracy and precision. Criteria the preliminary study, it can be concluded that iodine at food matrices could be determined using epithermal NAA.

The calcinator furnace in PSTA-BATAN is currently installed with ON-OFF temperature controller to maintaning temperature changes in calcination process. Calcination is a process of heating a substance at high temperature in stages but still below its melting point to remove its impurities. The ON-OFF temperature controller using a relay as the power switching for AC voltages applied on furnace electric heat element when the temperature exceeds or below the set point temperature. The contactor movement in relay will cause a sudden surge of voltages and currents which could lead to the thermal shock or unstable heating rates and unstable holding time. In this paper, the ON-OFF method was developed into Proportional Integral Derivative (PID)-based which has simple structure and robust performance for phase angle controlling in AC voltages applied on furnace electric heat element to controlling the temperature in multi stages by using Arduino Nano as the microcontroller.

In today's of the conventional cancer diagnosis, there are still many problems encountered, such as the ineffectiveness of drug loading, instability, and biocompatibility issues. One alternative method for early detection of cancer is using nuclear techniques using radioactive compounds such as Technetium-99m. In the present research work, a silica mesoporous nanomaterial SBA-16-Al will be introduced as a carrier of imaging agent of radioactive compounds that play a role in radiation imaging. The Al-SBA-16 nanomaterials labeled with 99mTc (99mTc-SBA-16-Al) radioisotope exhibited very interesting nuclear properties for applications in imaging radionuclide diagnoses. Preparation by treatment of milling for 30 hours and ultrasonication bath for 60 minutes produced particle sizes of 510-3900 nm with a median of 1587 nm. Based on the results of this study, the optimum radiochemical purity was obtained at 85.66 ± 0.72% with pH 9 of solutions, the ratio of the amount of SnCl2 and SBA-16-Al to 75 μg compared to 1000 μg (1: 13.3), and incubation time during 20 minutes, with the radioactivity of technetium-99m ranging from 0.21 to 1.23 mCi. The results of the electrophoresis test showed that 99mTc-SBA-16-Al is a neutrally charged compound.

Air pollution has become a global concern because of its effects on the environment and human health. Nuclear analytical techniques (NATs) have important application in air pollution monitoring and research. NATs such as Instrumental neutron activation analysis (INAA), Particle Induced X-ray Emission (PIXE), X-ray fluoresence (XRF), and X-ray absorption near-edge structure (XANES) have been used in quantification of environmental pollutant especially airborne particulate samples (APM) collected from several cities in Indonesia. The samples were analysed for elemental concentrations by INAA at Siwabessy multipurpose reactor and Bandung TRIGA 2000 reactor in Indonesia, PIXE at Institute of Geological and Nuclear Sciences New Zealand, XRF at BATAN Bandung Indonesia, and Synchrotron facilities at Elettra Italy. The techniques provide more than 20 significant elements for identification the possible sources of atmospheric aerosol. The results demonstrated that INAA, PIXE, XRF and XANES can complement significantly the elemental characterization of APM providing the concentration of several major, minor and trace elements. These results can be used as important information on levels and sources of air pollution. It could also be used as an early warning, scientific research-based references in designing and revising various government policies and regulations related air quality standards in Indonesia.

A simulation of ion beam extraction and beam formation process for 150 keV/2mA ion implantor using SIMION 8.1. has been done. This simulation is aimed to provide an overview of the influence of the geometry and the effect of the variation of the voltage of both extractor and the acceleration tube of the ion source of ion implantor on the trajectory, beam diameter and beam emittance. The simulation was carried by varying the amount of particles that went through the acclerating tube, varying the accelerating voltage, and the extraction voltage, from 50 to 3000 particles, from 30 kV to 150 kV, and from 1 kV to 10 kV respectively. The simulation results show that the ion extraction process and the ion beam formation at the ion source of ion implantor is very dependent on the geometry and the voltage of both electrode and the extractor on the device. The incorrect electrode geometry and voltage would cause the particle trajectory to be non-linear, while the angle of the beam would diverge too much. We've also found that the amount of simulated particle would affect the homogeneity of the cross section of the beam. The bigger the amount of the simulated particle, the more homogeneous and stable the beam becomes. Unfortunately, for 3000 particles the running process was very long and prone to errors. Therefore in this simulation, the amount of particles is set to 2000, which gave us a rather uniform beam cross section. The variation of extraction voltage 1 kV to 10 kV while keeping the accelerating voltage constant at 150 kV produced an increment of the diameter of the ion beam from 3.84 cm to 4.12 cm. The variation of accelerating voltage from 30 kV to 150 kV while keeping the extraction voltage constant at 10 kV caused the spot diameter of the ion beam to increase. The value of the spot diameter of the ion beam when the accelerating voltage is kept at 150 kV are 4.12 ± 0.05 cm and 4.05 ± 0.05 cm for y-axis and x-axis respectively.

In the case of mesoporous silica nanoparticle applications for nuclear medicine, for example in the case of nanoparticle labeling, it is often found cases of radiochemical impurities or low labeling efficiency which may be caused by the bonding properties that occur. In this work, the adsorption isotherm and thermodynamic studies of Rhenium onto mesoporous silica nanoparticles have been performed to determine the parameters associated with the surface properties of mesoporous nanoparticle silica for labeling purposes. Adsorption measurements were performed by a batch technique with the various initial concentration of rhenium solution (5, 10, 25, 50, 75, 100, 125, 150, and 200 ppm) and conducted with constant stirring for 20 minutes at 28, 35 and 45°C, respectively. The results of the experiment were analyzed using UV-Vis spectrophotometer and through data calculations showed that the properties of rhenium adsorption onto silica mesoporous nanoparticles, among others, are exothermic (negative value of ΔH), spontaneous reactions (negative value of ΔG), and follow adsorption of chemisorption (ΔH value range -55,45 to -137,04 kJ/mol).

Testing and evaluation of velocity selector control system of small angle neutron scattering (SANS) spectrometer has been done. It applied a unit of speed control variable AC, Optidrive Invertek Drives. This system is designed to be manually controlled and computerized. To control the Optidrive in manual mode, it can be done by keypad on the unit. The Optidrives can be controlled using computer by connecting the unit into a computer via USB port and OptiTools Studio software. Optidrive Invertek Drives need alternative current (AC) voltage one phase 220 volt with three phase out 220 volt. This out voltage is used as voltage source for moving the motor of disk in SANS neutron velocity selector. The speed of the disk in SANS neutron velocity selector is changed by adjusting the frequency from the Optidrive Invertek Drives. The numbers of speed of the disk determine the neutron wavelength passed through SANS neutron velocity selector. It is observed that every increasing frequency of 1 Hz, it will increase the disk speed by 59.929 rpm. The calibration that has been done for this system using silver behenate, obtain wavelength of the neutrons dependent to the disk speed. They are 3.10, 3.09, 3.41, 3.76, 4.23, 4.71, and 5.39 Å for disk speed 6500, 6000, 5500, 5000, 4500, 4000, and 3500 rpm respectively.

Environmental radioactivity surveillance in a large area is undertaken commonly by using ground-based vehicle mounted gamma monitoring system or airborne gamma monitoring system. An alternative of using drone (unmanned aerial vehicle)-mounted gamma monitoring system may give advantages of saving resources and time, more rapid preparation and operation, fewer and safer operators, better access coverage area, and more flexible adjustment of flight parameters. A prototype of drone-mounted gamma monitoring system is under development in BATAN. The design of the system will consist of drone module and other modules mounted in the drone e.g. radiation detection module of a simple and lightweight CdZnTe gamma detector system that expected to be equivalent to one inch of NaI(Tl) in efficiency, position monitor module with a GPS, a telemetry-based data communication system with a radio frequency (RF) module for collecting data of radiation level, position coordinates, visual data locations and real time transfer to a receiver module located in a station where the data acquisition and analysis module will also be positioned. This paper reports the latest status of design development of the drone mounted gamma monitoring system based on the results of partial testing of the capacity characteristics of the drone module and the developed data transfer and receiver modules for the radiation levels and position coordinates.

Separation the zircon mineral from tailing tin mining using a shaking table. Zircon mineral has been separated from the Bangka Belitung tin mine tailings by shaking table. The process stage begins with draining the water until the flow is in a stable state, followed by loading the material through the feeder. The results of the process in the form of concentrate were dried in the oven at 105 °C. This research studied the effects of water discharge, feed rate, and the tilt angle of the shaking table. The results obtained were the optimum water discharge at 17 liters per minute, the feed rate was 15 kg per minute with a tilt angle of the shaking table was 10°. In these conditions, the recovery results obtained were 88.80 %.

Mixing tank system is main part of STTN-BATAN mini plant which functions to mix two liquid materials from tank 1 and tank 2 into tank 3. At present, proccess in mixing tank system has not fully worked automatically. Where, operator must be operated one by one for the process sequence. This results in the mixing process become less homogeneous. The purpose of this research is to build an automation of mixing tank system in STTN-BATAN mini plant using DCS Centum VP software to get better homogenous. This research began with the creation of new project in Centum VP software, creating HMI displays, DCS programming, and automation testing in STTN-BATAN mini plant. Before optimization, it was shown that the average excess fluid from tank-1 to tank-3 is 6.252 mmH₂O, from tank-2 to tank-3 is 5.272 mmH₂O. After optimization, better results are obtained. It was shown that the average excess liquid from tank-1 to tank-3 is 1.178 mmH₂O, from tank-2 to tank-3 is 1.33 mmH₂O.

In this study, as a part of the development of the radiation mapping technology, we are planning to develop the gamma-ray imager based on a passive detector such as a dosimeter. For this purpose, we demonstrated the use of nanoDot OSLD as a passive detector being irradiated inside a soft x-ray machine then combined the irradiation position (qualitatively) with radiation dose (quantitatively) for visualization purpose. The experimental results showed that the NanoDots exhibit good linearity and reproducibility when subjected to soft X-rays machine, Hence, the nanoDots showed a promising potential for visualization of dose distribution.

Milling machine is one of the conventional machine that capable of working on a flat surface, side cuting upright, leaning even the making of grooves and gear. This work on machine tools or finish a workpiece using milling knife (cutter) as chisel cut rotating on the axis of the machine. Welding is one of the important process in the manufacture of sample for industrial use. Friction stir welding one of welding techniques without welding medium. The welding process from this technique is obtained from the combination of heat and pressure due to friction between the spindle and the welding materials. Study on friction stir welding is carried out using a milling machine 3 axis with spindle as a tool for welding processes. The test materials Al and Mg alloy.The sample is positioned steady in sample holder, while the spindle spins welding instrument. Welding is carried out using the Y direction of the engine with a direct corner frais welding processes of 1o. Z-axis direction is used to immerse the spindle holder between two stir welding material to be in the welding, as for the direction of the X-axis is keep stable in its position. Spindle shaft dimension D = 25 mm, L = 100 mm spindle shaft, spindle las D = 5 L = 5, 4 mm. The speed of rotation of the engine use a two-speed variation, i.e 1450rpm and 180rpm. In this research, the result show that using 180rpm of the speed rotation engine with the feeding speed is 1,3 mm/min, and the temperature 55° C,is the optimum condition for welding of Al alloy by Mg, The welding surface look smooth without any cracks contour, as well as the level of its homogeneity of material both look almost reached a percentage of 50:50.

Research and studies on pebble bed fuel to support the realization of RDNK based on HTGR have been carried out by BATAN. Indicators of reliability of nuclear fuel are able to fulfill the criteria for irradiation testing and qualify in post irradiation tests. At present, Radiometallurgy Installation as a post irradiation examination location has completed installation of X-ray radiography equipment for non-destructive testing. Performance analysis includes the function of tools and the completeness of test support facilities. Digital X-ray radiography has a maximum voltage capability of 320 kV. X-rays are directed vertically towards the sample and sensor film. X-rays captured by film sensors can be seen directly in real time on a computer. To put the pebble bed fuel is provided a special holder. The X-ray radiography system trials were carried out on a pebble bed fuel model. The purpose of the trial to find out the performance of X-ray radiography systems in capturing the image of the pebble bed fuel model. The fuel model is made of ceramic which simulates graphite and lead material that simulates TRISO. The results obtained indicate that the X-ray digital radiography system is able to capture the image of the pebble bed fuel model with a good image.

Neutronic analysis of comparation UN-PuN fuel and ThN fuel for 300MWth Gas Cooled Fast Reactor long life without refueling has been done. Gas Cooled Fast Reactor is a Generation IV reactor with gas coolant (i.e. helium) and using fast spectrum neutron. The neutronic calculation was carried out using SRAC (Standard Reactor Analysis Code) version 2006 under the Linux Operating System with nuclear data library JENDL4.0. The first calculation is fuel pin cell calculation (PIJ-method) by using a hexagonal cell and then followed by the calculation of the core reactor (CITATION-method). The calculation of the core reactor used homogeneous and heterogeneous core configuration. The UN-PuN fuel use plutonium as a fissile material and natural uranium as a fertile material and the ThN fuel use U233 as a fissile material and natural thorium as a fertile material. The percentages of fissile material are varied in heterogeneous core configuration. It is used to decrease the peaking power in the center of the core. The heterogeneous core configuration contains of Fuel 1 (F1) 8% fissile materials, Fuel 2 (F2) 10% fissile materials, and Fuel 3 (F3) 12% fissile materials. F1 is located in the central core, F2 middle core and F3 outer core. The diameter and height active core are 240 cm and 100 cm. The reflector radial-axial width is 50 cm. All of the calculations can reach burn up time more than 20 years with excess reactivity less than 1 percent (Δk/k <1%) both UN-PuN fuel and ThN fuel. It means that the reactor stable in 20 years. The average of power density both of UN-PuN fuel and ThN fuel are around 66 Watt/cc. The maximum power density of UN-PuN fuel is 94Watt/cc and ThN fule is 129Watt/cc. The UN-PuN fuel has lower maximum power density value than ThN fuel. So, for fast neutron spectrum reactor especially Gas Cooled Fast Reactor type, it is better used UN-PuN fuel than ThN fuel.

The purpose of this research is to identify and characterize the main and trace metals in plant (cassava leaves and grass) and soil. Results of the characterization was used to determine the transfer factor (TF) of metal absorption from soil to plant around Adipala power plant located in Cilacap Regency. Measurement of metal concentrations were carried out using instrumental neutron activation analysis techniques. Samples were irradiated in Rabbit and Lazy Susan system facility at the Kartini research reactor located in Centre for Accelerator Science and Technology. Irradiated samples then counted using HPGe detector. Concentration values for heavy metals were below the maximum recommended value stated by WHO and FAO. Transfer factor (TF) is used to assess the concentration of metals in cassava leaves and grass taken from soil. The TF value calculated in this research were below 1, this implied that cassava leaves and grass were safe from the risk of heavy metals. The highest transfer factor value is Sb, it showed that is Sb was more mobile compare to other metals.

Around Rembang Power Plant, ambient air samples of PM2.5 and PM10 has been taken. Result of this study can be useful as information for stakeholder and also people around Rembang power plant. Total characterization of average mass concentration in 6 locations for PM 2.5 and PM10 are 17.08 μg/m3 and 27.38 μg/m3 respectively. Those values are below air quality requirement by WHO. According to WHO, PM 2.5 should not exceed 25 μg/m3 and PM10 is not more than 50 μg/m3. Mass of PM 2.5 was around 63% from PM10 mass. This data shows that fossil fuel is main source of suspended particulate matter around Rembang power plant. Radioactivity analysis was done using gamma spectrometry, HPGe detector, radioactive sources (Eu-152 and Cs-137) and also Maestro 2 software. Radioactivity of Ra- 226 for PM2.5 and PM10, are 5.72 μBq/m3 and 7.30 μBq/m3 respectively. Radioactivity of Th-232 for PM2,5 and PM10 are 1.17 μBq/m3 and 2.59 μBq/m3 respectively, while radioactivity of K-40 for PM2.5 and PM10 are 17.68 μBq/m3 and 25.58 μBq/m3, respectively. Those values of radioactivity are below recommended values released by Regulation of Nuclear Regulatory Agency Head Number 7 Year of 2017 About Radioactivity Level in Air. According to this law, radioactivity of Ra-226 is below 1800 μBq/m3 and for Th-232 is below 2300 μBq/m3.

Environmental radiation monitoring especially around nuclear facility is needed to ensure public protection and safety. An online radiation monitoring system which continuously detects the presence of radioactive material in the environmental is important system to quickly detects uncontrolled radioactive released to the air. In this study, a radiation detection device based-on NaI(Tl) scintillation detector as part of an online radiation monitoring system has been developed and tested. During field testing, radiation count rate, and operational condition parameters which are temperature and relative humidity was collected continuously for 3 months. Data was transferred every 10 seconds with average communication delay around 0.57 second. Total number of data points is 733,725 records, and the average count rate was 653.09 cpm (σ = 81.77). Measured temperature is between 18.9 °C and 44.3 °C, while relative humidity is between 19.4 %RH and 78.6 %RH. Experimental result shows that count rate has temperature dependence. Effect of temperature to the count rate was estimated using power equation, and then the equation is used to correct the measurement data. After correction, several peaks which indicates the presence of radioactive material other than background radiation can be identified easily. In the future, further development such as radionuclide identification feature can be added to the prototype.

Exploration and production of tin massively has an impact in the quantity of tailing production. The tailing contains various strategic metal-carrying minerals, namely monazite, xenotime, zircon and ilmenite. By the right process, these minerals can be purified into high-value metals such as rare earth elements, Zr and Ti. The research purpose is conducting a study towards processing and refining technology of tin tailing. The study was performed by analyzing the composition of Bangka tin tailing using XRF. Based on these information, flow diagram of processing and refining technology of monazite to Ce₂O₃, La₂O₃ and concentrated Nd(OH)₃; xenotime to concentrated Y₂O₃; zircon to ZrO₂; and ilmenite to TiO₂ have been generated. The result showed that processing and refining of tin tailing mining contained mineral monazite, xenotime, zircon and ilmenite could be carried out. However, it is still necessary to further develop the process by giving highly attention to the economic concept.

Nuclear analytical technique such as EDXRF has been widely used for elemental analysis of airborne particulate matters (APM). EDXRF Epsilon5 has been installed and commissioned in Center for Applied Nuclear Science and Technology-BATAN Bandung, Indonesia. Measurement conditions has to be set up to determine several elements: Al, Ca, Cu, Fe, K, Pb, S, Si, Ti and Zn. Optimization was carried out by optimizing the excitation conditions covering the tube voltage, tube current, secondary target, and analysis time. Method validation of EDXRF Epsilon5 was determined using Standard Reference Material (SRM) NIST 2783 Air Particulate on Filter Media for ensuring the reliability on APM analysis. Four measurement conditions with variation setting of tube voltage, tube current, secondary target, and analysis time were defined for several elements. The results of the selected elements were in a good agreement with the certified values. Replication of analysis using air particulate on filter media reference material using EDXRF Epsilon5 were considered as valid, accurate and reliable data.

Quality assurance of analytical results has become the high market demand in this globalization era. Accurate and reliable for analytical data is one of the requirements for a testing laboratory to get recognition from customers and institutions that issue certificates, which may be obtained by ensuring the validity of the used analytical methods. Validation of methods applied by laboratories can be done; one of by conducting proficiency tests or inter-laboratory comparative tests. We have been conducted the Inter-laboratory comparative tests for Neutron Activation Analysis for elemental characterization of coal fly ash. Coal fly ash samples were prepared according to ISO Guide 34 and 35, and distributed to eleven NAA laboratories in Indonesia as well as in other countries. As much as 18 elements should be analyzed by participant laboratories. The results were processed statistically using Z-score where it found that three elements (Hg, Se, and Mg) cannot be evaluated due to insufficient data and also high variations of the data, while for other elements such as As, Th, Na, and Sb showed a good agreement among participant laboratories. Through this inter-laboratory comparative testing program, it is expected that NAA laboratories, especially in BATAN, can maintain and improve their performance and quality of their analytical results.

High background radiation areas usually are correlated to the high concentration of primordial radionuclides activity from Uranium/Thorium series and ⁴⁰K. This paper reported the natural radioactivity level in soil sample was taken from Botteng Utara village area. The activity of primordial radionuclide such as ²²⁶Ra, ²³²Th and ⁴⁰K were investigated from the soil by gamma spectrometry. In order to evaluate the radioactivity levels of the area, Radium equivalent activity (Ra_eq), the absorb dose rate (D), the annual effective dose rate (E), the external hazard index (H_ex), and internal hazard index (H_in) were calculated and compared with the internationally approved value. The concentration of ²²⁶Ra, ²³²Th and ⁴⁰K measured by gamma spectrometry are lies in the range 268.90 to 2921.17, 993.07 to 3153.81, and 115.72 to 438.26 Bq.kg⁻¹respectively. The average and maximum annual effective dose received by Botteng Utara resident from terrestrial gamma rays are 10.40 and 18.62 mSv y⁻¹, which is the maximum received by resident of Tande-Tande hamlets. This present work clarify that Botteng Utara is an area with high background radiation exposure from primordial radionuclides activity.

Neutron Activation Analysis (NAA) is a nuclear analytical technique for elemental analysis that has been widely applied in various fields such as environment, industry, health and food. It has high specificity and sensitivity for the analysis of elements with very low concentrations up to the picogram order. In Indonesia, NAA technique was developed in BATAN that has a research reactor as a neutron source. Relative method of NAA that uses the multi-elements standard as a comparison is widely used in Indonesia. At present, BATAN is developing an absolute method k0-NAA that has several advantages such as faster and more economics due to the reduction of multi-elements standard dependence. BATAN k0 Utility (BAkUL) beta version software has also been developed for data processing of the absolute methods. k0-NAA requires reactor parameters (α and f) as well as detector parameters for data analysis. The parameter f is the ratio of the thermal neutron flux to the epithermal whereas α is the epithermal spectrum deviation parameter from the 1/E distribution. The aim of this study is to measure parameters a and f using the triple bare monitor method by irradiating simultaneously Au and Zr without Cd cover. Measurement of reactor TRIGA 2000 parameters (α and f) were carried out at the irradiation positions CT1-1 and G17-2, and the results for α and f parameters at the CT1-1 irradiation position were -0,100 and 8.22 respectively, while at the G17-2 position was - 0.087 and 13.8. Each irradiation position has different α and f values so it is necessary to determine the reactor parameters for other irradiation positions. The measurement results α and f can be used for the next samples irradiation and as a database to support the application of the k0-NAA method in Center for Applied Nuclear Science and Technology (PSTNT) BATAN.

Particulate is one indicator of air pollutants derivative from a complex mixture of large and small particles that are decomposed. Particulate diameter at 2.5 to 100 mm consists of dust originating from agriculture, building construction, and vehicles. Particulates with a diameter of less than 2.5 mm are generally made from fossil fuels and vehicle exhaust containing various specific chemicals or ions. In this activity, characterization of chemical content and specific ions in fine particulates was carried out in fine air particulate samples by ion chromatography. Sampling was carried out in several regions in Indonesia such as Pekanbaru, PalangkaRaya, Manado, Ambon, Jayapura, Denpasar, and Surabaya. The validation methods using reference materials. On the other hand, verification of measurements is carried out regularly with ED-XRF therefore accurate and precise quality can be obtained. The results of this activity obtained several cations and anions such as Ca²⁺, K⁺, Mg²⁺, Na⁺, SO₄^2-, NO₃⁻, F⁻, and Cl⁻. The results obtained from this activity are expected to be used as basic data and scientific-based references for regional/national in formulating, taking appropriate and directed actions and policies to solve the problem of air pollution.

The e-tongue in this study was developed in 16 lipid membrane-based sensor channels. Each membrane lipid arrange by different polymer membranes. Membranes are made by combining polyvinyl chloride (PVC) as a matrix. Four different types of plasticizers (2-NPOE, bis (2-Ethylhexyl) Pthalate, bis (2-Ethylhexyl) phosphate, bis (1-butyl pentyl) adipate). Four types of lipids (octadecylamine, oleyl alcohol, methyltrioctylammonium chloride, and oleic acid) for active ingredients. This electronic tongue is used to classify river water pollution in Malang City from various sources. The data obtained were analysed using the PCA (Principal Component Analysis) method. Based on the PCA score plot shows the value of PC1 = 49.18%, and PC2 = 20.09%. Based on the loading plot shows the sensors that have the greatest contribution in classifying river water pollution are sensor 5, sensor 6. The PCA pattern shows that the river in front of UIN Malang, the river around Sumbersari and the river around Landungsari have a very close pattern. The data obtained show that the source of pollution of the three rivers is almost the same. The river around Soekarno Hatta and the river around Merjosari have a different pattern from the other three rivers. It can be concluded that using the PCA method can distinguish the classification of river water in different places.

This research investigated the crystal structure, magnetic susceptibility, and biocompatibility of the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles for x = 0%, 1.00%, 1.25%, 1.50%, and 1.75%. The hydrolysis method was employed to produce the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles from natural calcite. The crystal structure and magnetic susceptibility of the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles were characterized by means of X-ray diffraction (XRD) and susceptibility meter, respectively. The elemental data analysis presented that the natural calcite as the main precursor contained calcium of 98.84%. Moreover, the diffraction data showed that the increase in Gd content decreased the lattice parameters and crystal volume of the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles. The magnetic character of the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles changed from diamagnetic to paramagnetic as the increase of Gd content. Interestingly, the increasing Gd content enhanced the magnetic susceptibility of the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles. Furthermore, the nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles had an excellent biocompatibility. Therefore, the prepared nano-sized Ca_10-xGd_x(PO₄)₆(OH)₂ particles open a potency to be applied for biomedical treatment.

The improvement of the batik industry besides having a positive influence on improving the economy and the welfare of the community also has negative impacts. One of the negative impacts is the emergence of batik industry waste water in quite large quantities. Therefore the use of natural dyes is seen as an alternative effort in terms of minimizing the quantity of batik waste. The batik production process involves heavy metal elements so that the waste also contains heavy metal elements which can potentially pollute the environment. Some batik industries in Yogyakarta do not yet have a waste treatment plant so that the waste is directly discharged into the environment. In this study an analysis of heavy metal elements contained in natural dyes are Tegeran (Cudrania Javanensis) and Jalawe (Terminalia bellirica) by the neutron activation analysis method and enumeration was carried out using a spectrometry detector conducted at Centre of Science and Accelerator Technology-Yogyakarta. This Research state that some metal element Tegeran (Cudrania Javanensis are Th-227, Gd- 161, Kr-88, Na-24,I-135 dan K-40. While Metal elemen in Jalawe (Terminalia bellirica) are Th-227, Rh-104, Ir-192, Br-84, Tl-208, I-135, Eu-152, I-134, Y-92 dan K-40. The use of natural dyes with optimal fixation will produce different color variations. This is because the bonding of metal elements with each metal type in the fixator will form different chemical bonds. It is hoped that by analyzing the metal content of natural dyes, batik performers can use natural dyes optimally and can minimalize wastewater in batik industry. The first section in your paper.

MZFe₂O₄ (Z = Zn; M = Mn) ferrofluids based on olive oil as liquid carrier was successfully prepared by coprecipitation route. The stability of the MZFe₂O₄ ferrofluids was maintained by using oleic acid as surfactant agent. Their morphology, crystal structure, fractal structure, and optical behaviours were investigated by means of SEM, XRD, SAXS, and UV-Vis spectroscopy. Furthermore, the potency as antibacterial agent of the MZFe₂O₄ ferrofluids was explored by dilution method. The analysis for the XRD data presented that the MZFe₂O₄ particles as fillers constructed in nanometric scale with cubic spinel structure. The SEM images of the MZFe₂O₄ powders tended to agglomerate with spherical shape. Moreover, the MZFe₂O₄ ferrofluids constructed complex structure with aggregated fractal originated by interaction of internal force of magnetic particles. Theoretically, such phenomenon is predicted as the effect of filler, surfactant, and liquid carrier in the ferrofluids. Interestingly, the MZFe₂O₄ ferrofluids demonstrated superior performance as antibacterial agent than those of MZFe₂O₄ nanopowders. Technically, the superior performance of the ferrofluids is believed from its significant enhancing inhibition zone diameter as the effect of olive oil as an appropriate carrier.