Development of a program to calculate the amount of steam leakage from nuclear reactor piping under the leak before break event
Creators
- 1. Central Research Institute of Electric Power Industry, Energy Transformation Research Laboratory, Materials Science Division, Yokosuka, Kanagawa (Japan)
Description
The Central Research Institute of Electric Power Industry (CRIEPI) has developed a probabilistic fracture mechanics (PFM) code 'PEDESTRIAN' for nuclear reactor piping. Unfortunately, the current code does not have a function to calculate the amount of steam leakage at the time of an event, that is one of effective indicators to determine the severity of the event. On the other hand, some foreign PFM codes developed for similar purpose have the function to evaluate the amount of steam leakage in the form of subroutines or dedicated subprograms. Therefore, we originally developed 'LEECPIPE' to calculate the amount of steam leakage during an event with reference to similar foreign code LEAPOR. Then, verification analyses were performed for both LEAPOR and LEECPIPE to reproduce the experiment described in the reference for another program, SQUIRT, and those were compared with the experimental results and the SQUIRT calculations. As a result, the maximum relative error was approximately 33% for SQUIRT and for LEAPOR, whereas the maximum relative error was approximately 17% for LEECPIPE. (author)
Availability note (English)
Available from https://criepi.denken.or.jp/hokokusho/pb/reportDownload?reportNoUkCode=EX23002&tenpuTypeCode=30&seqNo=1&reportId=10019Additional details
Additional titles
- Original title (Japanese)
- 原子炉配管の破断前漏えい蒸気量計算プログラムの開発
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- CRIEPI-EX--23002
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 56003046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CRACKS; CRITICAL FLOW; DETERMINISTIC ESTIMATION; FAILURES; L CODES; LEAKS; NUCLEAR POWER PLANTS; PIPES; PROGRAMMING; REACTOR COOLING SYSTEMS; STEAM; STRESS CORROSION; THERMAL HYDRAULICS; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; CORROSION; ENERGY SYSTEMS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 20 refs., 8 figs., 4 tabs.