경수로 사용후핵연료 재포장시설 내 주요 설비 개념설계
Conceptual Design of Key Equipment in Encapsulation Plant for PWR Spent Nuclear Fuel
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This study presents the conceptual design of key equipment for an encapsulation plant intendedfor the final disposal of pressurized water reactor (PWR) spent nuclear fuel (SNF). Due to differences in designstandards between dry storage and disposal systems, SNF must be repackaged into dedicated disposal casks priorto emplacement. The design was developed by considering domestic storage and disposal conditions, as well asanticipated throughput. The plant is composed of ten functional zones, including cask receiving, canister cutting, fuelhandling, disposal cask welding, and decontamination. Major equipment required for each zone was identified andconceptually designed based on functional requirements, performance specifications, and relevant design codes. Coresystems such as the overhead crane, bolt tightening/loosening manipulator, clamshell cutting station, fuel handlingsystem, friction stir welding system, and decontamination chamber were configured to support remote operation,shielding, and automation under high-radiation environments. Design parameters were derived by referencingboth the specifications of canisters from domestically promising dry storage systems and the disposal cask conceptproposed through a national radioactive waste management R&D project. International standards such as KEPIC,ASME, ANSI, and ISO were applied. The proposed design is expected to ensure ALARA-level radiation protection,improve operational efficiency, and serve as a foundational reference for advancing high-level radioactive waste(HLW) management programs in Korea.
Abstract
This study presents the conceptual design of key equipment for an encapsulation plant intendedfor the final disposal of pressurized water reactor (PWR) spent nuclear fuel (SNF). Due to differences in designstandards between dry storage and disposal systems, SNF must be repackaged into dedicated disposal casks priorto emplacement. The design was developed by considering domestic storage and disposal conditions, as well asanticipated throughput. The plant is composed of ten functional zones, including cask receiving, canister cutting, fuelhandling, disposal cask welding, and decontamination. Major equipment required for each zone was identified andconceptually designed based on functional requirements, performance specifications, and relevant design codes. Coresystems such as the overhead crane, bolt tightening/loosening manipulator, clamshell cutting station, fuel handlingsystem, friction stir welding system, and decontamination chamber were configured to support remote operation,shielding, and automation under high-radiation environments. Design parameters were derived by referencingboth the specifications of canisters from domestically promising dry storage systems and the disposal cask conceptproposed through a national radioactive waste management R&D project. International standards such as KEPIC,ASME, ANSI, and ISO were applied. The proposed design is expected to ensure ALARA-level radiation protection,improve operational efficiency, and serve as a foundational reference for advancing high-level radioactive waste(HLW) management programs in Korea.
