Published 2004 | Version v1
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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)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

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