Published May 2014 | Version v1
Miscellaneous

Analysis of Long Term Core Cooling Capability of the APR1400 Considering LOCA Generated Debris

  • 1. KHNP Central Research Institute, Daejeon (Korea, Republic of)

Description

The fibrous materials may collect on the bottom nozzle of fuel assembly (FA) and would seriously impede flow into the core. Chemical products could be deposited on the surface of cladding. The debris effect causes a problem to remove decay heat from the core with the coolant. The concern described above is a real challenge to provide for long term core cooling (LTCC) capability. In this study, an analysis of LTCC capability for APR1400 considering the effect of LOCA generated debris has been performed using the RELAP5 code. In this paper, the long term core cooling capability of the APR1400 was evaluated with the effect of LOCA generated debris. The partial inlet blockage model and the chemical deposition model were adopted to simulate the effect of LOCA generated debris. The results indicate that the long term core cooling capability of the APR1400 can be maintained in the safe state after ECCS switchover to recirculation from the sump. The peak cladding temperature of the hot channel shows at much lower level than the critical temperature of the cladding

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
[2 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
46050588
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; COOLING; FISSION PRODUCTS; FLOW BLOCKAGE; FUEL ASSEMBLIES; LOSS OF COOLANT; NOZZLES; PWR TYPE REACTORS; R CODES; REACTOR CORES; SURFACES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DEPOSITION; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 6 figs, 1 tab