Severe accident analysis for Wolsung nuclear power
- 1. KEPRI, Taejon (Korea, Republic of)
Description
Severe accident analysis has been performed for the Wolsung nuclear power plants in Korea to investigate severe accident phenomena of CANDU-600 reactors as a part of Level II PSA study. The accident sequence analyzed in this paper is loss of active heat sinks (LOAH) which is caused by loss of off-site power, diesel generators, and DC power, ISAAC(Integrated Severe Accident Analysis Code) computer code developed by KAERI (Korea Atomic Energy Research Institute) was used in this analysis. This paper describes the important thermal-hydraulics and source term behaviors in the primary system and inside containment, and the failure mechanisms of calandria vessel and containment. In addition, some insights for accident management program (AMP) are also given
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting Vol. 1
- Imprint Pagination
- 622 p.
- Journal Page Range
- p. 464-470
Conference
- Title
- 1997 spring meeting of the Korean Nuclear Society
- Dates
- 30-31 May 1997
- Place
- Kwangju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33056579
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- HYDRAULICS; I CODES; PROBABILITY; REACTOR ACCIDENTS; SOURCE TERMS; THERMAL ANALYSIS; WOLSUNG-1 REACTOR
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; FLUID MECHANICS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MECHANICS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 5 refs, 12 figs, 1 tab