Published May 2011 | Version v1
Miscellaneous

Evaluation on the Conservative Critical Flow Model in SPACE Code using Marviken Test

  • 1. Korea Hydro and Nuclear Power Company, Daejeon (Korea, Republic of)

Description

The alpha version of the SPACE code, which is the best-estimate safety analysis code, has been developed, and its verification and validation are in progress. The SBLOCA (Small Break Loss-of-Coolant Accident) evaluation methodology for the APR1400 (Advanced Power Reactor 1400) is also under development using the SPACE code. The goal of the development is to set up a conservative evaluation methodology in accordance with Appendix K of 10CFR50 by the end of 2012. To develop the Appendix K version of the SPACE code, modification of the code is considered through the implementation of the required evaluation models. At present, the Moody model for the conservative prediction of the discharge flow under a two-phase condition is in effect as a look-up table in the SPACE code. In this paper, the implemented conservative critical flow model in the SPACE code is preliminarily assessed against Marviken test

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2011 spring meeting of the KNS
Dates
26-27 May 2011
Place
Taebaek (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42099171
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CRITICAL FLOW; EVALUATION; LOSS OF COOLANT; PWR TYPE REACTORS; S CODES; SAFETY ANALYSIS; TWO-PHASE FLOW; VALIDATION; VERIFICATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 4 figs, 1 tab