Published 1989
| Version v1
Book
High level vibration test of nuclear power piping
Creators
- 1. Nuclear Power Engineering Test Center, Tokyo (Japan)
- 2. Japan Atomic Power Co., Tokyo (Japan)
- 3. Tokyo Electric Power Co., Inc. (Japan)
- 4. Kansai Electric Power Co., Inc., Osaka (Japan)
- 5. Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan). Takasago Works
- 6. Mitsubishi Heavy Industries Ltd., Kobe (Japan). Kobe Shipbuilding and Engine Works
- 7. Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan)
- 8. Brookhaven National Lab., Upton, NY (USA)
Description
A series of seismic capacity tests of nuclear power piping have been performed to investigate elastic-plastic response characteristics and obtain additional data concerning the ultimate limit of a piping system subjected to earthquake excitations. The test model was designed by modifying the 1/2.5 scale model of a PWR primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run
Additional details
Additional titles
- Subtitle (English)
- Test procedure and test results
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 967 p.
- Series
- Seismic response analysis and design.
- Journal Page Range
- p. 745-750.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21079929
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FRACTURE MECHANICS; HAZARDS; PIPES; REACTOR COMPONENTS; REACTOR SAFETY; SEISMIC EFFECTS; TESTING
- Descriptors DEC
- MECHANICS; SAFETY
Optional Information
- Secondary number(s)
- CONF-890855--.