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PGSFR BOP계통 배관 응력평가 적용방안 고찰

Considerations of Stress Assessment Methodology for BOP Pipings of PGSFR

  • 오영진 (한국전력기술(주) 미래전력기술연구소) ;
  • 허남수 (서울과학기술대학교) ;
  • 장영식 (한국전력기술(주) 미래전력기술연구소)
  • 투고 : 2016.05.31
  • 심사 : 2016.06.27
  • 발행 : 2016.06.30

초록

NSSS (Nuclear Steam Supply System) and BOP (Balance of Plant) design works for PGSFR (Prototype Gen-IV Sodium Fast Reactor) have been conducted in Korea. NSSS major components, e.g. reactor vessel, steam generator and secondary sodium main pipes, are designed according to the rule of ASME boiler and pressure vessel code division 5, in which DBA (Design by Analysis) methods are used in the stress assessments. However, there is little discussions about detail rules for BOP piping design. In this paper, the detail methodologies of BOP piping stress assessment are discussed including safety systems and non-safety system pipings. It is confirmed that KEPIC MGE(ASME B31.1) and ASME BPV code division 5 HCB-3600 can be used in stress assessments of non-safety pipes and class B pipes, respectively. However, class A pipe design according to ASME BPV code division 5 HBB-3200 has many difficulties applying to PGSFR BOP design. Finally, future development plan for class A pipe stress assessment method is proposed in this paper.

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참고문헌

  1. American Society of Mechanical Engineering, ASME Boiler and Pressure Vessel Code, Section III, Division 5, "High Temperature Reactors", 2015.
  2. American Society of Mechanical Engineering, ASME Boiler and Pressure Vessel Code, Section III, Division 1, 2015.
  3. American Society of Mechanical Engineering, ASME Code B31.1, "Power Piping", 2012.
  4. American Society of Mechanical Engineering, Companion guide to the ASME Boiler & Pressure Vessel Code, Chapter 16. B31.1, Power piping, 2009.
  5. American Society of Mechanical Engineering, ASME Boiler and Pressure Vessel Code, Section II, Part D, 2015.