Published 1989
| Version v1
Book
Effect of Coulomb friction on dynamic response of reactor pressure vessel system under extreme loadings
Creators
- 1. Westinghouse Electric Corp., Pittsburgh, PA (USA)
- 2. Westinghouse Electric Corp., Columbia, SC (USA)
Description
In the dynamic analysis of nuclear power plants, it may be necessary to include sliding and lift-off in the mathematical model of the nuclear supply system. This is due to the fact that various equipment and components are generally not fastened to adjacent structural members or to the supporting foundation and, therefore, may slide or lift- off when subjected to extreme loads. This paper presents a nonlinear transient dynamic time history analysis of a pressurized water reactor (PWR) vessel and its internals subjected to seismic loads
Additional details
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. 569-576.
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
- 21080186
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FRICTION; HAZARDS; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR VESSELS; RESPONSE FUNCTIONS; SEISMIC EFFECTS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; FUNCTIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.