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Study of structure systems and components classification of Reaktor Daya Eksperimental - RDE based on life cycle management

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Published under licence by IOP Publishing Ltd
, , Citation Endiah Puji Hastuti et al 2019 J. Phys.: Conf. Ser. 1198 022048 DOI 10.1088/1742-6596/1198/2/022048

1742-6596/1198/2/022048

Abstract

Reaktor Daya Eksperimental (RDE) is a pebble-fueled, gas-cooled non-commercial power reactor having thermal power of 10 MW that will be constructed in PUSPIPTEK Serpong. The objective of the small-scale power reactor is to demonstrate to general public the utilization and safety features of nuclear power reactor. Aging management of a nuclear installation should have been considered since the design, construction, commissioning phase and operation phase as well. It is expected that, in designing structure, system, and components (SSC) of a nuclear installation, material quality selection, component design life cycle, surveillance plan, and maintenance schedule in accordance with its purpose should be carried out carefully. As a consequence, if this SSC fails, it can give significant impact to environment. Classification of component of RDE planned by Indonesia is not available yet. Therefore, this paper describes RDE component classification with regard to life cycle management. SSC classification is carried out based on IAEA's Safety Guide, and regulations in effect in Indonesia as well as life cycle management. The screening of SSC candidates that have been identified based on aging object easiness of refurbishment, it's found that there are eight critical SSCs of RDE. The reactor core and internals are the critical SSC that has the most critical components of aging mechanism assessment.

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10.1088/1742-6596/1198/2/022048