Published December 2015
| Version v1
Journal article
Suggestion for system improvement of the AP1000 based on PSA results
Creators
- 1. China Nuclear Design Company Shanghai Branch, Shanghai (China)
Description
Based on the APlOOO level one Probabilistic Safety Assessment, the vulnerability of the normal residual heat removal system could lead to the high contribution of the initiating event of SI-LB. The Improvement of the normal residual heat removal system has been made. A fault tree and related event tree model of the RNS are rebuilt by the Probabilistic Safety Assessment methodology; the RNS system reliability and the contribution of the improvement on the CDF are analyzed. The results show that after the improvement of the RNS, the contribution of the SI-LB is greatly decreased and the core damage frequency is reduced by 29.1%. (authors)
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 35
- Journal Issue
- 4
- Journal Page Range
- p. 723-728
- ISSN
- 0258-0918
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 50051132
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; DAMAGE; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR CORES; RELIABILITY; RHR SYSTEMS; RISK ASSESSMENT
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 figs., 2 tabs., 4 refs.