Published May 2015 | Version v1
Miscellaneous

Estimation of Fracture Parameters for Leak-before-Break Assessment on Elevated Temperature

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

Description

When the liquid sodium leaks this interaction may cause the fire that is harmful to safety of the reactor. Therefore, it is necessary to prevent against sodium fire in SFRs. Leak-before-Break(LBB) concept, had been devised for this purpose and has following advantage than Double-ended Guillotine Break(DEGB) design. If DEGB is excluded, the number of extinguish facilities and firewalls against the sodium fire can be minimize. LBB concept, has been well established and had many experience in regard of light water reactors(LWRs). But LBB assessment to SFRs is more complicated because SFRs is operated on elevated temperature region. On this region, because creep damage occurs to material and grows defects LBB assessment to SFRs should be considering creep effects. The procedure and method for this purpose are provided RCC-MRx A16 that is France code. To calculate fracture parameters such as K and J are required to some coefficients and equations which have been limited in RCC-MRx A16. Thus, in this study obtained K and J using finite element analysis for the sub-model including the crack. In this study, fracture parameters for LBB assessment were estimated by finite element analysis. This result will be applicable to LBB assessment of PGSFR

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023210
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CREEP; EQUATIONS; FINITE ELEMENT METHOD; FRACTURES; LEAKS; R CODES; SAFETY; SODIUM COOLED REACTORS; USES; WATER COOLED REACTORS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; FAILURES; LIQUID METAL COOLED REACTORS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; REACTORS

Optional Information

Notes
5 refs, 6 figs, 1 tab