WIND project tests and analysis on the integrity of small size pipe under severe accident condition
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
Description
In a severe accident of a light water reactor(LWR), fission products (FPs) released from fuel rods will be transported to the primary cooling system piping as aerosol and some of them will be deposited on the inner surface of piping. In such conditions the primary cooling system piping might be subjected to both of elevated temperature load due to decay heat of FPs and pressure load, and as a consequence the integrity of piping might be threatened. The WIND (Wide Range Piping Integrity Demonstration) Project is being performed at Japan Atomic Energy Research Institute (JAERI) to investigate the FP aerosol behavior in reactor piping and the integrity of reactor piping under severe accident condition (K. Hashimoto et al., 1994, K. Hashimoto et al., 1995). In order to meet these two objectives, the Project comprises two test series: an aerosol behavior test series and a piping integrity test series. In the piping integrity test a straight stainless steel pipe is used to simulate a partial fraction of reactor piping under severe accident conditions. In parallel with conducting the tests, test analyses are performed with ABAQUS code (Hibbitt, Karlsson and Sorensen Inc. 1989) using the test conditions to investigate the behavior of straight pipe against thermal and pressure loads. This paper describes the comparison of the scoping piping integrity test results and the analysis results with ABAQUS
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 3: Safety and reliability
- Imprint Pagination
- 595 p.
- Journal Page Range
- p. 199-203.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27063002
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DEPOSITION; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; PIPES; PRIMARY COOLANT CIRCUITS; RADIOACTIVE AEROSOLS; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; RELIABILITY; THEORETICAL DATA; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; COOLING SYSTEMS; DATA; DISPERSIONS; EVALUATION; INFORMATION; NUMERICAL DATA; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; SOLS
Optional Information
- Secondary number(s)
- CONF-960306--.