Published 1999
| Version v1
Miscellaneous
Operability enhancement for PWR by relaxation of safety design parameters
Creators
- 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Description
The risk analysis was performed in order to extend the surveillance test interval (STI) of RPS/ESFAS from 1 month to 3 months. The results showed that core damage frequency (CDF) increase 1.47% for Kori units 3,4 and 1.19% for Yonggwang units 1,2 when the surveillance test interval is increased. The analysis report was submitted to regulatory body and the approval of relaxation of STI was obtained recently. 5 refs., 4 tabs
Additional details
Publishing Information
- Imprint Title
- The 21st KAIF-JAIF seminar on nuclear industry
- Imprint Pagination
- 444 p.
- Journal Page Range
- p. 71-78
Conference
- Title
- 21. KAIF-JAIF seminar on nuclear industry
- Dates
- 18-19 Oct 1999
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 31000728
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- PARAMETRIC ANALYSIS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REPUBLIC OF KOREA; RISK ASSESSMENT; SAFETY ANALYSIS; STEAM GENERATORS
- Descriptors DEC
- ASIA; BOILERS; DEVELOPING COUNTRIES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS