Taipower's approach in development of in-house LOCA analysis capability
Creators
- 1. Power Research Institute, Taiwan Power Company, Taipei County, Taiwan (China)
Description
One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, so, a technology transfer program and a training program of a new LOCA analysis methodology for Taipower's engineers is briefly described in this paper. Also, an other lesson learned from the TMI accident was the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval, so, a study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Maanshan nuclear power plant. The results of the 4 inch line break LOCA analysis is described in this paper. (author)
Files
35097847.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 30A1-30A6
- Report number
- INIS-XA-N--081
Conference
- Title
- 4. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 5-8 Apr 1994
- Place
- Taipei, Taiwan (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35097847
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; LOSS OF COOLANT; MAANSHAN-1 REACTOR; RISK ASSESSMENT; SAFETY ANALYSIS; THREE MILE ISLAND-2 REACTOR; US NRC
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This record replaces 35095580; 7 refs, 9 figs, 2 tabs