Published October 2017 | Version v1
Miscellaneous Metadata-only

Analytical Investigation of APR1400 SBLOCA Using MARS-KS Code

Creators

  • 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

The possibility of core uncovery and significant reheat due to loop seal clearing and reformation phenomena was considered as one of the safety issues by USNRC in the review of design certificate for APR1400. Therefore, it is needed to perform the independent audit calculation to review the results of safety analysis on APR1400 SBLOCA with changed codes and the raised issue explained above. In this study, the transient behavior of APR1400 SBLOCA was analyzed with MARS-KS code. The thermal-hydraulic phenomena including loop seal clearance and reformation was observed so that its effect on core cooling capability and safety margin were identified.

Part of:
Proceedings of the KNS 2017 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2017 Fall Meeting of the KNS
Dates
25-27 Oct 2017
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49079075
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COOLING; DESIGN; LOSS OF COOLANT; M CODES; PWR TYPE REACTORS; S CODES; SAFETY ANALYSIS; SAFETY MARGINS; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 5 figs, 1 tab