Published May 2002
| Version v1
Miscellaneous
A study on improvement of PHWR safety analysis methodology through LBLOCA assessment for Wolsong Unit 2
- 1. Seoul National Univ., Seoul (Korea, Republic of)
- 2. Handong Univ., Pohang (Korea, Republic of)
- 3. KINS, Taejon (Korea, Republic of)
Description
The assessment of the cooling capability of the emergency core cooling system (ECCS) in Wolsong Unit 2 for large loss of coolant accident (LLOCA), 35% break at the feeder pipe near the core entry, was performed to establish the safety regulation criteria for pressurized heavy water reactors (PHWRs). According to the results, the ECCS was estimated to be sufficient capability for LLOCA. However, the three dimensional power distribution in core should be considered in the safety analysis. Besides, it is also concluded that the determination of critical pass location and study of nuclear physics and thermal hydraulic characteristics in the critical pass during the accident should be also included in the safety analysis
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS-KARP Joint spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [12 p.]
Conference
- Title
- 2002 joint spring meeting of the KNS-KARP
- Dates
- 23-24 May 2002
- Place
- Gwangju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 34009717
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLING SYSTEMS; LOSS OF COOLANT; NUCLEAR PHYSICS; PHWR TYPE REACTORS; PIPES; POWER DISTRIBUTION; REACTOR CORES; SAFETY ANALYSIS; WOLSUNG-2 REACTOR
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; ENERGY SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 4 refs, 17 figs, 2 tabs