• 제목/요약/키워드: ANSI/ANS-57.1

검색결과 2건 처리시간 0.019초

원전설비 등급분류 방법론 분석 (Analysis of classification standards of nuclear facilities)

  • 제상윤;장윤석;오창식;최영환
    • 한국압력기기공학회 논문집
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    • 제14권1호
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    • pp.48-57
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    • 2018
  • Configuration management (CM) is the process of identifying and documenting characteristics of plant structures, systems and components (SSCs), and of ensuring that changes to these characteristics are properly assessed, approved, implemented, verified and recorded. The purpose of this study is to examine regulation and technical standards developed under different concepts and level of depth for classification of nuclear SSCs as an essential prerequisite of the CM. In this context, main contents of currently adopted NSSC Notice 2016-10 are reviewed and compared with those in recently published ANSI/ANS 58.14 and IAEA SSG-30. The technical standards were prototypically used for classification of O-rings in two nuclear systems. It is found that ANSI/ANS 58.14 results in different categories taking into account specific features while IAEA SSG-30 leads to same categorization of the O-rings. Key findings will be summarized for Korean regulatory amendment in the future.

Code Requirements for Fuel Handling Equipment at Nuclear Power Plant

  • Chang, Sang-Gyoon;Kang, Tae-Kyo;Kim, Jong-Min;Jung, Jong-Pil
    • 방사성폐기물학회지
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    • 제20권1호
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    • pp.119-126
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    • 2022
  • This study provides technical information about the nuclear fuel handling process, which consists of various subprocesses starting from new fuel receipt to spent fuel shipment at a nuclear power plant and the design requirements of fuel handling equipment. The fuel handling system is an integrated system of equipment, tools, and procedures that allow refueling, handling and storage of fuel assemblies, which comprise the fuel handling process. The understanding and reaffirming of detailed code requirements are requested for application to the design of the fuel handling and storage facility. We reviewed the design requirements of the fuel handling equipment for its adequate cooling, prevention of criticality, its operability and maintainability, and for the prevention of fuel damage and radiological release. Furthermore, we discussed additional technical issues related to upgrading the current code requirements based on the modification of the fuel handling equipment. The suggested information provided in this paper would be beneficial to enhance the safety and the reliability of the fuel handling equipment during the handling of new and spent fuel.