DOI QR코드

DOI QR Code

Preliminary Leak-before Break Assessment of Intermediate Heat Transport System Hot-Leg of a Prototype Generation IV Sodium-cooled Fast Reactor

소듐냉각고속로 원형로 중간열전달계통 고온배관의 파단전누설 예비평가

  • Received : 2016.06.01
  • Accepted : 2016.06.27
  • Published : 2016.06.30

Abstract

Recently, the research and development of Sodium-cooled Fast Reactors (SFRs) have made progresses. However, liquid sodium, the coolant of an SFR, is chemically unstable and sodium fire can be occurred when liquid sodium leaks from sodium pipe. To reduce the damage by the sodium fire, many fire walls and fire extinguishers are needed for SFRs. LBB concept in SFR might reduce the scale of sodium fire and decrease or eliminate fire walls and fire extinguishers. Therefore, LBB concept can contribute to improve economic efficiency and to strengthen defense-in depth safety. The LBB assessment procedure has been well established, and has been used significantly in light water reactors (LWRs). However, an LBB assessment of an SFR is more complicated because SFRs are operated in elevated temperature regions. In such a region, because creep damage may occur in a material, thereby growing defects, an LBB assessment of an SFR should consider elevated temperature effects. The procedure and method for this purpose are provided in RCC-MRx A16, which is a French code. In this study, LBB assessment was performed for PGSFR IHTS hot-leg pipe according to RCC-MRx A16 and the applicability of the code was discussed.

Keywords

References

  1. RCC-MRx code Section III Subsection Z Appendix A16, 2012, Guide for prevention of fast fracture, Leak before Break analysis and defect assessment, Afcen.
  2. R6-revision 4, 2000, Assessment of the integrity of structures containing defects, British energy.
  3. RCC-MRx code Section III Subsection Z Appendix A3, 2010, Properties groups for materials - general, Afcen
  4. Report of the U.S. Nuclear Regulatory Commission Piping Review Committee, 1984, Evaluation of Potential for Pipe Breaks, NUREG-1061 Volume 3.
  5. Y. J. Kim, J. H. Jae, J. S. Kim, D. J. Kim, H. W. Kim, 2015, Evaluation of Leak-Before Break for IHTS of PGSFR, KAERI/CM-2214