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The ALARA (an acronym for 'as low as reasonably achievable') principle, keeping the likelihood of incurring exposure, the number of people exposed and the magnitude of their individual doses 'as low as reasonably achievable, taking into account economic and societal factors', is at the core of radiation protection. For many decades the principle has been an area of continuous development, with recent work highlighting the importance of engaging not only with the decision-makers in the ALARA process but all stakeholders who may incur an exposure. This paper considers a particular case study in which the dredging of non-hazardous sediment in the United Kingdom near a now decommissioned nuclear power station raised substantial public concern about radiological exposure. This turned what was a straightforward construction activity into a complex public engagement and reassurance task, at a significant cost disproportionate to the level of radiological risk. This paper highlights the key lessons learnt from the case study, including not only the importance of engaging the public as part of the ALARA process but also of considering the societal impact arising from stress and concerns if misinformation is allowed to promulgate. A discussion is included on the need to underpin any engagement with a clear plan, including pre-engagement, implementation and reinforcement of messages. In addition, the role of the radiation protection professional is considered in ensuring that all stakeholders are informed, so that ultimately they can come to their own decision on what is safe.

Ongoing national programmes and International forums have in recent decades developed and enhanced methods and strategies in how to address the characterisation of potentially suitable sites for radioactive waste repositories. Siting processes, site selection and site investigation programmes have been conducted for near surface and geological repositories and plans for construction are in progress or have already been implemented. Lessons learned from these national and international programmes are available and results are published. In this paper we synthesise the methods and our lessons learned in how to plan, conduct, and achieve site understanding. Effective site understanding should incorporate a multi-disciplinary and integrated view of geosphere and biosphere information for a site, together with the designed parts of a repository or installation that constitute the total system. We argue that this integrated approach, following a staged program of repository development and adopting a graded approach to assessment at each stage, is to be recommended. The recommendation is supported by the results of international cooperation and progress with national programmes (e.g. the Swedish SKB). Further, we argue that this strategy is valid as a foundation for planning and execution of other types of radioactive waste management programmes such as decommissioning, legacy site management and remediation projects.

This paper reports on a detailed investigation into the disposal procedures and records from the operational period (1960–1968) of the Little Forest Legacy Site (LFLS) in eastern Australia. The aims of the paper are firstly, to highlight the priority issues which are relevant to the radiological assessment of the LFLS, and secondly, to present key lessons that may help to guide future investigations of the records at similar sites. Particular effort was put into assessing the various types of relevant documents and the relationships between them. A specific objective of this work was to evaluate an inventory of the wastes which was reported shortly after the time of disposals. A major finding of the study is that the original actinide inventory for LFLS relied solely on estimates from a limited number of specific records known as 'Scrap Disposal Reports' (SDRs). For example, the estimated amount of plutonium disposed at the LFLS was based on only seven SDR records. Given that there are approximately 50000 buried items, it is possible that other Pu-contaminated items could make a significant additional contribution to the amount of Pu present at the site. For some waste components (e.g. beryllium) the documentation shows that rough estimates of disposal quantities were made, based on the number of disposed Be-contaminated items in each trench. The use of such approximations casts some doubt on the accuracy of the previous inventory of wastes at the site. In addition, the early summaries of radionuclide disposals, which categorized radionuclides into groups according to their radiological hazard, contained significant underestimates of the radionuclide inventory in the most hazardous category (referred to at the time as 'Group I' radionuclides). This was mainly due to the omission of the Pu (which had been recorded on the SDRs) from the Group I inventory, but was also in part because the Group I radionuclide content of disposed sludge drums (from a wastewater treatment plant) was not taken into account for most of the disposal period. Establishing the disposal history and radionuclide inventory at legacy sites is an important pre-requisite to evaluating their radiological impact and developing management options. The detailed investigation of the LFLS records shows the importance of understanding the operational practices of the period and the derivation of the original inventories. These insights should help guide future efforts to better understand disposal histories and inventories at LFLS and elsewhere.

A very large segment of the population is fearful of radiation, and sometimes rightly so. It is a word that conjures up images of something dangerous and invisible, and is often associated with the real fears of nuclear apocalypse that permeated the cold war era. TV dramas such as HBO's Chernobyl certainly fuel that fear response. Public response to radiological events, ranging from true emergencies such as the Fukushima Daiichi nuclear power plant accident in 2011 to benign events such as the bucket of uranium ore discovered at the Grand Canyon Visitor's Center in early 2019, highlight the need for effective public communication strategies. All too frequently when an event is not considered dangerous by scientists, we fail to capitalise on the opportunity for public engagement. Public communication and empathy are some of the most important challenges that the health physics and radiation protection community face today. Empathy is of particular importance in effective public communication- understanding and explaining the science in layman's terms is insufficient to widen public support. Rather, the ability to plainly explain the science must be coupled with an understanding of what the public or an individual is feeling about a particular issue. This requires more than science. This paper presents the Health Physics Society's Ask The Expert (ATE) feature, focuses on how ATE works, why it has been successful at building a culture of empathy, how ATE is adapting to the ever-changing public information consumption practices, and how the underlying principles ATE uses can be applied by the health physics community at large.

Large areas of the former British nuclear test site at Maralinga were contaminated by the explosive dispersal of plutonium. The Australian Government, in consultation with stakeholders, determined that the site should be cleaned-up so that it is fit for unrestricted habitation by the Aboriginal traditional owners (Maralinga Tjarutja). Engagement with the stakeholders, particularly the Maralinga Tjarutja, determined that the specific criterion for rehabilitation was 5 mSv y⁻¹ and that some restrictions on permanent occupancy should remain. Remediation of the site began in 1995, took 5 years and cost AU$106 million. The site was returned to its traditional owners in 2009 and is now the site of a flourishing tourism operation.

Comparison of tritium volume activity (VA) rates in objects of environment in the Mayak Production Association (Mayak PA) affected area in the period from 2014 to 2015 with tritium VA rates in the same or similar objects of environment measured in the period from 2001 to 2013. Water samples from environmental objects—precipitations, ponds, wells—were the material for this research. Tritium VA in various environmental objects was measured using liquid scintillation method. The results were processed using parametric and nonparametric methods of statistical analysis. In samples collected in 2014–15 from open reservoirs located in Mayak PA affected area tritium VA was 1.4 times lower than the level of tritium VA in water samples from the same reservoirs collected in 2001–03. There was no statistically significant difference between tritium VA in water samples from the same open reservoirs collected in periods 2009–12 and 2014–15. Tritium VA in the water sample from production reservoir R-2 (lake Kyzyltash) in 2015 made 11 200 Bq l⁻¹ that was 1.7 times higher than average rate in 2007–09. In water samples collected in 2014 from 11 wells and boreholes located in the affected area of Mayak PA tritium VA made in average 22 ± 5 Bq l⁻¹. No statistically significant difference was detected in water samples taken from boreholes in 2005–06 and in 2014. Comparison of median values revealed a statistically significant 3.2 times decrease of tritium VA in samples of daily precipitations in Ozyorsk in the time interval between 2007 and 2014. In single samples of daily precipitation in 2007, 2014 and 2015 tritium VA in Ozyorsk made 1020, 145 and 3500 Bq l⁻¹ respectively that in respect exceeded the median values 29 times in 2007, 13 times in 2014 and 160 times in 2015. This could indicate irregular tritium air emissions from Mayak PA that provides ground for necessity of tritium VA monitoring not only in daily precipitation but also in air vapor condensate. Decrease of tritium VA in water samples from open reservoirs from the period of 2001–03 to 2014–15 as well as decrease of the levels of tritium VA in samples of daily precipitation from 2007 to 2014 could be an evidence of possible decrease of tritium atmospheric emission from Mayak PA.

The process of nuclear weapons production from 1949 to 1987 was accompanied by the generation of a great amount of radioactive waste. Waste processing operations and controls on discharges at this time were not to the same standard as today. Because of this, vast areas of the Urals region of Russia surrounding the Mayak Production Association (MPA) were exposed to routine and accidental radioactive contamination. The greatest contribution to the contamination was gas aerosol emissions from the MPA in the 1950s (total activity 38 PBq, mainly ¹³¹I), releases of liquid radioactive waste into the Techa River from 1949 to 1956 (total activity 115 PBq, including long-lived ⁹⁰Sr and ¹³⁷Cs) and accidental atmospheric releases as a result of the thermochemical explosion of the storage tank for liquid radioactive waste in 1957 (74 PBq, relatively short-lived radionuclides being the main contributors). Protective measures helped to relieve the pressing problem of population safety in the 1950s and 1960s, but they led to the appearance of new sources of contamination in the territory surrounding the MPA—Lake Karachay (total activity of beta-emitters 4400 PBq) and the Techa Cascade of Reservoirs (TCR; total activity 8 PBq). Owing to natural radioactive decay and rehabilitation measures, the radiation situation in the East Urals Radioactive Trace (EURT) has improved considerably over the years. Economic activity has been partially restored in these territories. Only the most contaminated territory of the East Urals Radioactive Reserve cannot be used for any economic activities up to the present day. Marked non-uniformity of radioactive contamination of the EURT and the Techa River floodplain, as well as radionuclide washout from Lake Karachay and the TCR into the underground waters and the Techa River require on-going radioecological monitoring, management and regulatory supervision.

My task is to consider whether haematopoietic cell transplants would be considered appropriate today in persons with features like victims of high-dose and dose-rate ionizing radiations after the Chernobyl nuclear power facility accident in 1986 given knowledge and experience gained over the past 35 years. First I consider the conceptual bases for considering an intervention appropriate and then the metric for deciding whether a transplant is appropriate in similar persons. Data needed to support this decision-making process include estimates of dose, dose-rate, dose uniformity, synchronous or metachronous injuries, donor availability and alternative interventions. Many of these co-variates have substantial uncertainties. Fundamental is a consideration of potential benefit-to-risk and risk-to-benefit ratios under conditions of substantial inaccuracy and imprecision. The bottom line is probably fewer transplants would be done and more victims would receive molecularly-cloned haematopoietic growth factors.

In 2016, the International Commission on Radiological Protection (ICRP) launched Task Group 103 (TG 103) for the explicit purpose of developing a new generation of adult and pediatric reference computational phantoms, named 'mesh-type reference computational phantoms (MRCPs)', that can overcome the limitations of voxel-type reference computational phantoms (VRCPs) of ICRP Publications 110 and 143 due to their finite voxel resolutions and the nature of voxel geometry. After completing the development of the adult MRCPs, TG 103 has started the development of pediatric MRCPs comprising 10 phantoms (male and female versions of the reference newborn, 1-year-old, 5-year-old, 10-year-old, and 15-year-old). As part of the TG 103 project, within the present study, the skeletal systems, one of the most important and complex organ systems of the body, were developed for each phantom age and sex. The developed skeletal systems, while closely preserving the original bone topology of the pediatric VRCPs, present substantial improvements in the anatomy of complex and/or small bones. In order to investigate the dosimetric impact of the developed skeletons, the average absorbed doses and the specific absorbed fractions for radiosensitive skeletal tissues (i.e. active marrow and bone endosteum) were computed for some selected external and internal exposure cases, which were then compared with those calculated with the skeletons of pediatric VRCPs. The comparison result showed that the dose values of the pediatric MRCPs were generally similar to those of the pediatric VRCPs for highly penetrating radiations (e.g. photons >200 keV); however, for weakly penetrating radiations (e.g. photons ⩽200 keV and electrons), significant differences up to a factor of 140 were observed.

The International Commission on Radiological Protection (ICRP) recently adopted a detailed biokinetic model for systemic iodine with reference transfer coefficients based on typical worldwide dietary intakes of stable iodine. The regional data provided demonstrate that the ICRP reference thyroidal biokinetics may differ substantially across regions with atypically low or high dietary intakes of stable iodine. Importantly, the design of the ICRP model facilitates modifications of reference thyroidal kinetics based on regional dietary iodine intake. The present study extended the ICRP model to the South Korean population, whose dietary iodine intake is much higher than the global mean. The following three transfer coefficients were selected as targets for Korean-specific values: thyroidal uptake rate (λ₁), hormonal secretion rate (λ₄) and leakage rate of thyroidal organic iodine as inorganic iodide (λ₅). The Korean-specific values for λ₁, λ₄ and λ₅ were determined to be 4.48, 0.0086 and 0.0171 d⁻¹, respectively, to yield the measurements of thyroidal iodine and physiological status of Korean adults. The determined λ₁ and λ₅ values differed noticeably from the ICRP values, whereas the λ₄ value was comparable to that of the ICRP. Compared with the ICRP reference model, the Korean model, in which the Korean-specific transfer coefficients were adopted, predicted noticeably lower thyroidal uptake and faster decrease of thyroidal iodine. In addition, the predicted cumulative activities of radioiodine in the thyroid were substantially lower (40–80%) than those predicted by the ICRP model. The Korean model developed in this study demonstrates that the iodine biokinetics for Koreans (i.e. a population with a high iodine consumption) obviously differ from the prediction of the ICRP model. Hence, the Korean model may serve to improve the accuracy of thyroid dose estimation for Koreans and will lead to practical changes in matters concerned with radiological protection.

Ground robotic vehicles are often deployed to inspect areas where radioactive floor contamination is a prominent risk. However, the accuracy of detection could be adversely affected by enhanced radiation signal through self-contamination of the robot occurring over the course of the inspection. In this work, it was hypothesised that a six-legged robot could offer advantages over the more conventional ground robotic devices such as wheeled and tracked rovers. To investigate this, experimental contamination testing and computational Monte Carlo simulation techniques (GEANT4) were employed to understand how radioactive contamination pick-up on three different robotic vehicles would affect their detection accuracy. Two robotic vehicles were selected for comparison with the hexapod robot based on their type of locomotion; a wheeled rover and a tracked rover. With the aid of a non-toxic fluorescent tracer dust, the contamination received by the all three vehicles when traversing a contaminated area was initially compared through physical inspection using high definition cameras. The parametric results from these tests where used in the computational study carried out in GEANT4. A cadmium zinc telluride detector was simulated at heights ranging from 10 to 50 cm above each contaminated vehicle, as if it were mounted on a plinth. Assuming a uniform activity of 60 Bq cm⁻² on all contaminated surfaces, the results suggested that due to the hexapod's small ground-contacting surface area and geometry, radiation detection rates using an uncollimated detector are likely to be overestimated by between only 0.07%–0.12%, compared with 3.95%–8.43% and 1.75%–14.53% for the wheeled and tracked robot alternatives, respectively.

¹⁷⁰Tm is being explored as a source for applications in brachytherapy. Although it has adequate physical properties, such as a short half-life (128.6 d), high specific activity and a mean photon energy of about 66 keV, it has a drawback of low photon yield (only about six photon emissions/100 beta emissions). The objective of this work is to study the dosimetric characteristics of a locally developed ¹⁷⁰Tm brachytherapy seed source using the Monte Carlo-based EGSnrc code system. In this study, we calculate the dose rate constant, air-kerma strength, radial dose function, anisotropic function and 2D dose-rate distributions in water. Separate simulations are carried out by considering the photon (gamma and characteristic x-ray) and beta spectra of the source. For regions close to the source (surface of the source < r < 0.4 cm), the dose is solely due to direct dose deposition by beta particles. At larger distances (0.4 cm < r <10 cm), the dose is due to bremsstrahlung photons produced by beta particles and photon emissions. The calculated value of the dose rate constant is 1.217 ± 0.052 cGy h⁻¹U⁻¹. The value of S_k per mCi is 0.029 ± 0.0009 U mCi⁻¹. The contributions of the inherent photon emission and the bremsstrahlung photons to the total S_k are 0.58 and 0.42, respectively.

This paper describes clearance as the sum of fractions (SOF) inequality with acceptable probability. We include scenario modelling uncertainties in SOF calculations. An illustrative contrast of results with and without the modelling uncertainties shows the differences in the probabilities that the standards were met. We present two methods for calculations, the analytical approach, GUM, and the Monte Carlo (MC) method. We prefer the MC. Inclusion of the scenario uncertainties can provide improved assurance that people are adequately protected. An example that used data from a Swedish reactor is included.

The two-filter method enables the continuous measurement of airborne Rn-222 via simultaneously sampling and counting. However, the slow time response of the two-filter detector and the overlapping counting data derived from the intervallic data acquisition make the interpretation of measurement results complicated. A valid data analysis to exactly match the series of counting data with the corresponding radon concentrations is desired. In this work, the continuous sampling and counting processes of the two-filter method is depicted numerically and the calculation of radon concentration from the raw counting data is given with detailed formulas. The numerical model is used to quantitatively investigate the influences of several key factors, including the volume of the radon delay chamber (5–10 000 l), the flow rate of air sampling (2.5–1000 l min⁻¹) and the interval time of data acquisition (5–120 min), on the measurement sensitivity and accuracy, which provides an approach for the optimization of the design and measurement settings of a specific two-filter detector in relation to these aspects.

During long-pulse deuterium plasma operations in the Experimental Advanced Superconducting Tokamak (EAST), a mixed radiation field is generated, which is mainly composed of fusion neutrons, gamma rays, and x-rays. More accurate and effective dose monitoring methods have been developed and established to determine the ionizing radiation intensity both for the stable operation of the device and for the radiation safety of personnel. As far as we know, there are few reports about the biological effects of radiation induced by fusion neutrons and γ radiation, which are of vital importance for the assessment of radiation hazards presented by fusion devices, such as EAST, to human beings and the environment. In this study, three positions in the EAST hall were selected to detect genotoxic effects induced by nuclear fusion radiation using a Vicia faba micronucleus (MN) test for the first time. The doses of neutrons and gamma rays at these places were measured by thermoluminescence dosimeters four times between June 2019 and May 2020. The radiation doses decreased as the distances from the EAST device shell gradually increased from S1 to S3. The radiation in the EAST hall resulted in a significant induction of MN in the Vicia faba root tip cells compared to a negative control, which was different from the MN frequency induced by fission neutrons, γ-rays and other kinds of radiation in previous studies. These results indicate the existence of potential genotoxic effects induced by radiation from EAST which is different from other radiation and suggest that personnel should not be permitted to enter the experimental hall during the discharge process, and that radiation protection measures should be taken during necessary maintenance to avoid radiation damage. These newly acquired results will certainly increase our knowledge about the biological effects induced by radiation from nuclear fusion and provide good data support for developing more effective environmental and personnel fusion radiation protection.

The objective of this study was to estimate the risk of radiation-induced injury to the organs due to ionizing radiation following breast screening recommendations employing digital breast tomosynthesis (DBT) and digital mammography (DM). Using the Monte Carlo method, absorbed doses in the tissues and organs were calculated on an adult female phantom, considering two-view craniocaudal (CC) and mediolateral oblique (MLO) projections for each breast. The results showed differences in the total effective risk due to DM (CC + MLO) and DBT (CC + MLO) examinations in Brazil, ranging from 20.73 cases 10⁻⁵ (DM) to 27.19 cases 10⁻⁵ (DBT). Significant differences were also observed in the total effective risk of cancer incidence in the lungs due to DM (CC + MLO) and DBT (CC + MLO), ranging from 1.75×10⁻⁰¹ cases 10⁻⁵ (DM) to 1.76×10⁻⁰¹ cases 10⁻⁵ (DBT). The results indicate that the total effective risk of incidence should be considered as an additional parameter for the evaluation of DBT or DBT + DM program performance.

The National Dose Registry (NDR) is owned and operated independently by Health Canada. This paper provides an overview of how the registry operates within the Canadian regulatory structure, followed by an analysis of annual effective dose trends in nine job classes with relatively higher mean annual effective doses, i.e. greater than 1 mSv as reported in 2017. The analysis showed that, with a few exceptions, mean annual effective doses have generally decreased or remained practically unchanged in the past two decades at relatively low exposure levels. This review of occupational dose trends is evidence of the effectiveness of radiation protection programmes in Canada. The NDR has played an important role in the identification of relatively higher dose records and allowed the regulatory bodies to act immediately to ensure appropriate actions were taken.

The motivation for this study was to explore a new method to test the particle spatial distribution for a therapeutic carbon beam. CR-39 plastic nuclear track detectors were irradiated to a 276.5 MeV u⁻¹ mono-energy carbon beam at the heavy ion facility in the Shanghai Proton and Heavy Ion Center. The spatial distribution of the primary carbon beam and secondary fragments in a water phantom were systematically analyzed both in the transverse direction (perpendicular to the projection direction of the primary beam) and at different depths in the longitudinal direction (along the projection direction of the primary beam) with measured tracks on the CR-39 detectors. Meanwhile, the theoretically spatial distribution and linear energy transfer (LET) spectra of the primary beam and secondary fragments were calculated using the Monte Carlo (MC) toolkit Geant4. The results showed that the CR-39 detectors are capable of providing high lateral resolution of carbon ion at different depths. In the range of the primary carbon beam, the beam width simulated with MC is in good agreement with that of experimental measurement. The track size registered in the CR-39 has a good correlation with the particle LET. These findings indicate that the CR-39 can be used for measuring both the particle flux and its spatial distribution of carbon ions.

Diagnostic reference levels (DRLs) are accepted as a dose optimisation tool for patients undergoing x-ray imaging and are required by South African (SA) legislation for 26 fluoroscopically guided procedures (FGPs). The aim of this paper is to collate all published SA data on DRLs in preparation for a project to establish national DRLs. Systematic searches were conducted of various applicable databases. All research that proposed DRLs for any imaging procedure in South Africa was included. Twenty-one works met inclusion criteria, the earliest from 2001. Two-thirds of all work reported on FGPs and five studies documented computed tomography DRLs. Three publications focussed exclusively on paediatric imaging DRLs. No studies on mammography or dental radiography were found. For clinical procedures with more than one proposed DRL, the range of proposed DRL varied by up to a factor of five. The highest proposed DRL is 373.1 Gy cm² for endovascular aneurysm/aortic repair procedures. Data were collected in six public hospitals and two private hospital groups. Thirty-six authors contributed to the manuscripts, but only six studies had an inter-disciplinary authorship. This is the first paper to provide a comprehensive review of SA DRL data and thereby advances international radiation protection initiatives. The data suggests there is room for more interdisciplinary work and that there must be rigorous standardization of reported parameters and data collection. This audit also highlights the need for standardized terminology, particularly for FGPs.

The International Commission on Radiological Protection (ICRP) recently reduced the dose limit for the eye lens for occupational exposure from 150 mSv yr⁻¹ to 20 mSv yr⁻¹, as averaged over defined periods of five years, with no annual dose in a single year exceeding 50 mSv, emphasizing the importance of the accurate estimation of lens dose. In the present study, for more accurate lens dosimetry, detailed eye models were developed for children and adolescents (newborns and 1, 5, 10, and 15 year olds), which were then incorporated into the pediatric mesh-type reference computational phantoms (MRCPs) and used to calculate lens dose coefficients (DCs) for photon and electron exposures. Finally, the calculated values were compared with those calculated with the adult MRCPs in order to determine the age dependence of the lens DCs. For photon exposures, the lens DCs of the pediatric MRCPs showed some sizable differences from those of the adult MRCPs at very low energies (10 and 15 keV), but the differences were all less than 35%, except for the posterior-anterior irradiation geometry, for which the lens dose is not of primary concern. For electron exposures, much larger differences were found. For the anterior-posterior (AP) and isotropic irradiation geometries, the largest differences between the lens DCs of the pediatric and adult phantoms were found in the energy range of 0.6–1 MeV, where the newborn lens DCs were larger by up to a factor of ∼5 than the adult. The lens DCs of the present study, which were calculated for the radiosensitive region of the lens, also were compared with those for the entire lens in the AP irradiation geometry. Our results showed that the DCs of the entire lens were similar to those of the radiosensitive region for 0.02–2 MeV photons and >2 MeV electrons, but that for the other energy ranges, significant differences were noticeable, i.e. 10%–40% for photons and up to a factor of ∼5 for electrons.

Ionising radiation (IR) is increasingly being used in diagnostic and therapeutic procedures and offers increased benefits to patients but poses an increased occupational health risk to operators. The consistent use and monitoring of radiation health care workers' dosimeters is an important part of the process for ensuring adequate monitoring and control of IR in the workplace. There is however often inconsistent dosimeter utilisation among these workers. The aim of this study was to report on the dosimeter utilisation and dosimetry practices in South African interventionalists. We conducted a survey and did in-depth and group interviews to evaluate dosimetry practices and the factors influencing these practices. We used STATA 15 to do a descriptive analysis of the quantitative data. A thematic analysis of the qualitative data was done using a deductive and inductive approach. There were 108 respondents (35 radiologists, 41 adult cardiologists, 32 paediatric cardiologists). The majority overall (65.8%), and in each category were males. The median age was 44 (interquartile range (IQR) 31–66)) and the median years worked with fluoroscopy was 10 years (IQR 1–32). Overall interventionalists (55%) ranked their perceived occupation risk as 2/10. Thirteen per cent of all interventionalists reported never using a personal dosimeter (PD), 58% reported wearing it >70% of the time. Inconsistent and inappropriate use of PDs emerged strongly from the qualitative data. There was poor dosimeter utilisation in this study. Participants were not aware of the role of medical physics departments. Evaluation of dosimetry practices as a means of monitoring and improving radiation safety in the catheterisation laboratory must be improved to create an improved culture of radiation safety and protection.

There is currently general concern over low-level radioactive wastewater from the development of nuclear industry. In this paper, a method based on an ultralow-level liquid scintillation spectrometer for measuring uranium radioactivity in low-level radioactive wastewater is proposed. This method can easily and quickly measure the radioactivity level of uranium in samples and can even distinguish the main isotopes of uranium. The liquid scintillation method directly provides results in units of radioactivity activity concentration, which are more convenient for comparison with relevant national standards to determine whether the emission standards are met. The lowest limit of detection of this method is 0.014 Bq l⁻¹ within 600 min.

In this study, a new ATCM phantom was developed to test the performance of the automatic tube current modulation (ATCM) of computed tomography (CT) scanners.. Based on the Chinese reference man and Monte Carlo simulations of x-ray attenuation, a more realistic ATCM phantom made of polymethyl methacrylate was developed. The phantom has a length of 20 cm, and it can be used to measure the dose profile along the central axis using 19 real-time MOSFET detectors. The image noise can be calculated slice by slice in the phantom's center. Test experiments showed that the phantom could initiate tube current modulation under different modulation levels of CT scans, and the actual effects of ATCM could be evaluated with the aid of the dose profile measurements. Using the measured dose profiles and image noise, the preferred dose can easily be identified from a choice of different modulation levels. The new phantom developed in this study can be used to test the ATCM performance of CT scanners, and is useful for further studies of the optimization of CT scan protocols with ATCM.

The PODIUM project aims to provide real-time assessments of occupationally exposed workers by tracking their motion and combining this with a simulation of the radiation field. The present work describes the approach that would be taken in mixed neutron-gamma fields, and details the methods for generating and applying an effective dose rate map; the required fluence to effective dose conversion coefficients at intercardinal angles are also presented. A proof-of-concept of the approach is demonstrated using a simple simulated workplace field within a calibration laboratory, with corroborative comparisons made against survey instrument measurements generally confirming good agreement. Simulated tracking of an individual within the facility was performed, recording a 1.25 μSv total effective dose and accounting for dose rates as low as 0.5 nSv h⁻¹, which is much lower than anything that could be accurately measured by physical neutron dosemeters in such a field.

Ring dosimeters for personal dosimetry are calibrated in accredited laboratories following ISO 4037-3 guidelines. The simultaneous irradiation of multiple dosimeters would save time, but has to be carefully studied, since the scattering conditions could change and influence the absorbed dose in nearby dosimeters. Monte Carlo simulations using PENELOPE-2014 were performed to explore the need to increase the uncertainty of ${H_{\text{p}}}\left( {{\text{0}}{\text{.07}}} \right)$ in the simultaneous irradiation of three and five DXT-RAD 707H-2 (Thermo Scientific) ring dosimeters with beam qualities: N-30, N-80 and N-300. Results show that the absorbed dose in each dosimeter is compatible with each of the others and with the reference simulation (a single dosimeter), with a coverage probability of 95% (k = 2). Comparison with experimental data yielded consistent results with the same coverage probability. Therefore, five ring dosimeters can be simultaneously irradiated with beam qualities ranging, at least, between N-30 and N-300 with a negligible impact on the uncertainty of ${H_{\text{p}}}\left( {{\text{0}}{\text{.07}}} \right).$

A study has been carried out to experimentally determine the calibration factor (CF) of the passive bronchial dosimeter, which consists of a direct radon progeny sensor capped with a 100-wire mesh. First, the CF was determined in controlled environmental conditions simulated in a calibration chamber. With aerosol concentrations varying from 10⁴ p cm⁻³ to 10⁵ p cm⁻³ and relative humidity varying from 60% to 80% in the chamber, CF was observed to be nearly constant with an average value of (3.8 ± 0.5) × 10⁻³ mSv tracks⁻¹ cm². Then, the CF was determined in real indoor environments in which it was again observed to be almost constant and the mean value was found to be (5.6 ± 0.1) × 10⁻³ mSv tracks⁻¹ cm². Pooling all the data on CFs obtained under controlled conditions and in real indoor environments, a lognormal distribution of the CF was observed with a geometric mean and geometric standard deviation of 0.0052 mSv tracks⁻¹ cm² and 1.28 respectively. The experimentally determined value of CF was found to be in close agreement with the theoretically estimated value, taking into consideration the unattached fraction of radon progeny. This dosimeter is passive, cheap, lightweight and, moreover, the CF being stable against environmental variations, will be useful in monitoring inhalation doses due to radon progeny for occupational workers.

The International Commission on Radiological Protection has recently published a report (ICRP Publication 147; Ann. ICRP50, 2021) on the use of dose quantities in radiological protection, under the same authorship as this Memorandum. Here, we present a brief summary of the main elements of the report. ICRP Publication 147 consolidates and clarifies the explanations provided in the 2007 ICRP Recommendations (Publication 103) but reaches conclusions that go beyond those presented in Publication 103. Further guidance is provided on the scientific basis for the control of radiation risks using dose quantities in occupational, public and medical applications. It is emphasised that best estimates of risk to individuals will use organ/tissue absorbed doses, appropriate relative biological effectiveness factors and dose–risk models for specific health effects. However, bearing in mind uncertainties including those associated with risk projection to low doses or low dose rates, it is concluded that in the context of radiological protection, effective dose may be considered as an approximate indicator of possible risk of stochastic health effects following low-level exposure to ionising radiation. In this respect, it should also be recognised that lifetime cancer risks vary with age at exposure, sex and population group. The ICRP report also concludes that equivalent dose is not needed as a protection quantity. Dose limits for the avoidance of tissue reactions for the skin, hands and feet, and lens of the eye will be more appropriately set in terms of absorbed dose rather than equivalent dose.

The Spanish Society for Radiological Protection (SEPR) is a scientific and technical organization that aims to bring together all radioprotection professionals from all the sectors of activity where ionizing and non-ionizing radiation is produced. The development of the SEPR's Strategic Plan every 5 years is the cornerstone of all the different activities that the Society carries out. This document establishes the SEPR goals and objectives for that period, as well as the activities planned to achieve them. It is a living and open document that draws on past experiences while looking to the future. The Strategic Plan 2019–2023, approved on June 2019, is the Third Strategic Plan of the SEPR. In its preparation, account has been taken of the experience obtained in the application of the two previous Strategic Plans, as well as of the new demands of the general public and of professionals in the area of radiological protection that have become apparent during the previous period. This paper describes the development of the current Strategic Plan, as well as the Plan itself, and briefly analyzes its implementation in the Conclusion.

The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has provided a detailed and authoritative update of its reviews of the epidemiology and dosimetry of radon and progeny. Lifetime risk of lung cancer calculated using data for several miner cohorts were 2.4–7.5 × 10⁻⁴ per working level month (WLM) of radon-222 progeny exposure for a mixed male/female population and 3.0–9.6 × 10⁻⁴ per WLM for a male population. Dosimetric models gave mean values of effective dose coefficients from radon-222 progeny of 12 mSv per WLM for mines, 16 mSv per WLM for indoor workplaces and 11 mSv per WLM for homes. The lifetime risk coefficient used by the International Commission on Radiological Protection (ICRP) is 5 × 10⁻⁴ per WLM and it has recently recommended an effective dose coefficient for radon-222 and progeny of 3 mSv per mJ h m⁻³ (about 10 mSv per WLM) for most circumstances of exposure. The ICRP risk and dose coefficients are supported by the UNSCEAR review and provide a clear and firm basis for current international advice and standards for protection from radon. Notwithstanding this evidence and the ICRP advice, UNSCEAR will continue to use a lower value of effective dose coefficient of 5.7 mSv per WLM for assessments of population exposures.

Cone beam computed tomography (CBCT) has been available since the late 1990s for use in dentistry. European legislation requires optimisation of protection and the use of diagnostic reference levels (DRLs) as well as regular quality control (QC) of the imaging devices, which is well outlined in existing international recommendations. Nevertheless, the level of application is not known. Earlier studies have indicated that few European countries have established DRLs and that patient doses (exposure parameters) have not been properly optimised. The EURADOS Working Group 12—Dosimetry in Medical Imaging undertook a survey to identify existing practices in Member States. Questionnaires were developed to identify equipment types, clinical procedures performed, and exposure settings used. The surveys were circulated to 22 countries resulting in 28 responses from 13 countries. Variations were identified in the exposure factors and in the doses delivered to patients for similar clinical indicators. Results confirm that patient doses are still not properly optimised and DRLs are largely not established. There is a need to promote the importance of performing QC testing of dental CBCT equipment and to further optimise patient exposure by establishment and use of DRLs as a part of a continuous optimisation process.

The radiation protection principles of justification, optimization, and dose limitation as enumerated by the International Commission on Radiological Protection have been guiding light for the profession for over three decades. The dose limitation does not apply to medical exposure but keeping patients' doses low is achieved through optimization, particularly by developing and using diagnostic reference levels (DRLs). There are new findings that demonstrate that despite using the best possible approaches to justification and optimization including as well use of DRLs, a very large number of patients are receiving doses in excess of 100 mSv of effective dose or organ doses exceeding 100 mGy. A non-ignorable fraction of patients is receiving such high doses in a single day. The magnitude of such patients creates the need for a relook into the principles with the intent to understand what can be done to attend to today's problems. A look at other areas such as approaches, and principles used in the pharmaceutical industry and in traffic management throws some light into what can be learnt from these examples. It appears that the system needs to be enriched to deal with the protection of the individual patient. The currently available approaches and even the principles are largely based on the protection of the population or group of patients. The third level of justification for individual needs further refinement to take into account series of imaging many patients are needing, and cumulative radiation doses involved, many of which happen in a short duration of 1 to 5 years. There is every likelihood of patient radiation doses continuing to increase further that underscores the need for timely attention. This paper provides several suggestions to deal with the situation.

As far as carcinogens are concerned, radiation is one of the best studied, having been researched for more than 100 years. Yet, radiation remains feared in many contexts as a result of its invisibility, its relationship with cancers and congenital disorders, aided by a variety of heuristics and reinforced by negative imagery. The strong socio-psychological response relating to nuclear energy has made radiation a classical case in the risk literature. This is reflected clearly following the nuclear accidents that have taken place, where the socio-psychological impacts of the clear dissonance between real and perceived health effects due to radiation exposure have caused considerable health detriment, outweighing the actual radiological impacts. Despite considerable efforts to normalise humankind's relationship with radiation, there has been little shift away from the perceived uniqueness of the health risks of radiation. One consistent issue is the failure to place radiation within its proper perspective and context, which has ensured that radiophobia has persisted. The radiation protection community must get better at placing its research within the appropriate perspective and context, something that is far too rarely the case in discussions on radiation matters outside of the scientific community. Each member of the radiation protection community has an ethical, professional and moral obligation to set the record straight, to challenge the misconceptions and factual errors that surround radiation, as well as putting it into the proper perspective and context. Failing to do so, the well-established harms of radiophobia will remain, and the many benefits of nuclear technology risk being withheld.