Published 1994 | Version v1
Book

Structural and seismic qualification of moderator system pump-motor units for RAPP-3, 4 and Kaiga-1, 2 235 MWe PHWRs

  • 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Division

Description

Smooth operation of active components like primary heat transport (PHT) pumps, moderator pumps, emergency core cooling pumps etc. is always required to ensure the safety of a nuclear power plant in case of normal as well as abnormal conditions. The moderator system pump-motor units for RAPP-3, 4 and Kaiga-1, 2 have been analysed theoretically to demonstrate the structural integrity of various components of the unit for various loadings as well as the functional requirement during an earthquake loading. The paper gives in detail the methodology adopted for both the analyses and their results. (author). 5 refs., 10 figs., 1 tab

Part of:
Pumping equipment in nuclear industry and thermal power plants: Proceedings of national symposium

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre.
Imprint Place
Bombay (India)
Imprint Title
Pumping equipment in nuclear industry and thermal power plants: Proceedings of national symposium
Imprint Pagination
[265 p.].
Journal Page Range
p. I.6-1-I.6-8.

Conference

Title
national symposium on pumping equipment in nuclear industry and thermal power plants.
Acronym
NSPE-94
Dates
24-25 Feb 1994.
Place
Bombay (India).

Optional Information