Seismic proving test of BWR primary containment vessel
Creators
- 1. Inst. of Industrial Science, Univ. of Tokyo, Tokyo (Japan)
- 2. Tokyo Univ. (Japan)
- 3. Tokyo Metropolitan Univ. (Japan)
- 4. Nagoya Inst. of Tech. (Japan)
- 5. Hitachi Ltd., Ibaraki (Japan). Hitachi Works
- 6. Mechanical Engineering Research Lab., Hitachi Ltd., Ibaraki (Japan)
- 7. Nuclear Power Engineering Test Center, Tokyo (Japan)
- 8. Seismic Dept., Nuclear Power Engineering Test Center, Tokyo (Japan)
Description
This paper reports on a seismic proving test that was conducted for a BWR Primary Containment Vessel (PCV), which is one of the most important facilities in a nuclear power plant, using a 1/3.2 scale model mounted on the large-scale high-performance vibration table of Tadotsu Engineering Laboratory, NUPEC. The test model was subjected to be the severest motion calculated for a standard 1100MWe BWR plant. The strength proving test confirmed the soundness of the structure and the resistance against earthquakes. Detailed analysis and analytic evaluation of the test data also confirmed the adequacy of the dynamic and earthquark response analysis method used in the present seismic design. Finally, the seismic safety and reliability of a BWR PCV of an actual plant were fully evaluated
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0510-7
- Imprint Title
- Seismic engineering 1990
- Imprint Pagination
- 315 p.
- Journal Page Range
- p. 215-222.
Conference
- Title
- 1990 pressure vessels and piping conference.
- Dates
- 17-21 Jun 1990.
- Place
- Nashville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23035325
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; DESIGN; EARTHQUAKES; ENVIRONMENTAL IMPACTS; NUCLEAR POWER PLANTS; REACTOR COMPONENTS; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; RELIABILITY; SAFETY ANALYSIS; SCALE MODELS; SEISMIC EFFECTS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; STRUCTURAL MODELS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900617--.