Large break loss-of-coolant accident analysis for China Qinshan-2 nuclear power plant
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
- 2. Nuclear Power Institute of China, Chengdu, SC (China)
Description
Large break LOCA analysis for China Qinshan-2 nuclear power plant has been performed using realistic evaluation model which has been being developed by KAERI. RELAP5/MOD3/KAERI code, which is a modified version of RELAP5/MOD3, is coupled with CONTEMPT4/MOD5 and is used as a best estimate code to predict the thermal hydraulic behavior of the system. PCT uncertainty which stems from code uncertainty, plant application uncertainty, scaling uncertainty and PCT bias are discussed. Among them, plant application uncertainty is described in detail. The licensing PCT is calculated by adding all the uncertainties to the best-estimate PCT. The result indicates the Qinshan-2 nuclear power plant has at least 37 deg C safety margin for large break LOCA. (Author) 10 refs., 47 figs., 14 tabs
Availability note (English)
MF available from INIS under the Report Number.Files
26060201.pdf
Files
(2.2 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 105 p.
- Report number
- KAERI-TR--480/94
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 26060201
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CHINA; COMPUTER CODES; LOSS OF COOLANT; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; ASIA; CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS