Published 1989
| Version v1
Book
Coupled seismic analysis of a pressurized heavy water reactor building
- 1. Bhabha Atomic Research Centre, Bombay (India)
Description
The conventional approach for the design of various equipments is to use the applicable floor response spectra generated from the reactor building model wherein the equipments are not modelled along with the civil structure. However, for major heavy equipments like primary steam generators, primary heat transport pumps, pressurizer, calandria-end shield assembly etc. of a PHWR, this may not be adequate as these equipments affect the response of primary structure and vice versa. A coupled analysis has been carried out to get a more realistic picture of stresses at the equipment supports. Effects of coupling/decoupling these equipments with reactor building have been studied and the results have been compared
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. 557-562.
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
- 21080219
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUILDINGS; HAZARDS; PHWR TYPE REACTORS; RADIOACTIVE WASTES; SEISMIC EFFECTS; SUPPORTS
- Descriptors DEC
- HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATERIALS; MECHANICAL STRUCTURES; RADIOACTIVE MATERIALS; REACTORS; WASTES
Optional Information
- Secondary number(s)
- CONF-890855--.