Published May 2014 | Version v1
Miscellaneous

Development of Procedures of Leak Before Break Assessment for Sodium Cooled Fast Reactor

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 2. Korea Univ., Seoul (Korea, Republic of)

Description

Double-Ended-Guillotine-Break(DEGB) in pipes can be prevented by detecting a leakage that occurs at the through-wall stage of a crack opening under those conditions. A consideration of these LBB characteristics can enlarge the degree of design freedom with respect to the materials, piping layouts, and safety measures against a leakage, thus leading to improved plant reliability and economy. For the LBB assessment of SFR pipes, creep crack growth could be considered, because SFRs are operated above 500 .deg. C. But the LBB assessment procedure for high temperature has not been established yet. In this study, we analyze RCC-MR A16 and propose procedure for the LBB assessment based on RCC-MR A16. For verification of this procedure, we conduct an example of LBB assessment. And we found partial procedure, equation and constant that has not been provided in RCC-MR A16. In this study, LBB assessment procedure has been proposed for SFRs design based on RCC-MR A16. Also, proposed procedure was verified by conducting an example assessment. As a result of those draw two conclusions as follow: · The LBB assessment of SFRs can be conducted by proposed procedure based on RCC-MR A16. · However, it is needed to develop determination of critical crack length methodology

Part of:
Proceedings of the KNS 2014 spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2014 spring meeting of the KNS
Dates
28-30 May 2014
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46050184
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CRACK PROPAGATION; CRACKS; CREEP; DESIGN; LEAKS; PIPES; RELIABILITY; RUPTURES; SODIUM COOLED REACTORS
Descriptors DEC
FAILURES; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; TUBES

Optional Information

Notes
6 refs, 6 figs