Development of Specific Safety Requirements for Radiological Protection of Korean Next Generation Reactors

Abstract

In this work specific safety requirements for radiological protection have been developed for Korean Next Generation Reactors (KNGR). Specific requirements of radiological protection, consistent with safety objectives, safety principles, and general safety criteria in the regulatory framework will be used to assess the safety of the KNGR. The requirements are divided into two categories, i.e., common design requirements and system design requirements. The common design requirements of ALARA are related to quantitative optimization. Key safety issues have also been derived, which should be reflected appropriately in relevant safety requirements. They are currently the incorporation of ICRP 60 recommendations and the monetary values for ALARA implementation. The system design requirements of radiation protection facilities are divided into those for shielding, radiation monitoring system, radiation management facilities, and systems interfaced with other systems.