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--.