Published 1994 | Version v1
Book

Main boiler feed pump for fast breeder test reactor. Failure analysis and remedial measures

  • 1. Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Reactor Operations Div.
  • 2. Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Power Plant Control Div.
  • 3. Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Engineering Development Div.

Description

A small capacity ten stage 670 kw feed water pump is used for supplying feed water at a temperature of 190 deg C to a once through steam generator in the Fast Breeder Test Reactor at Kalpakkam. During preparatory heating up stage to commission the steam generator the pump suffered a severe loss of suction which resulted in failure of hydrostatic journal bearings and extensive damage to pump internals. This paper discusses the detailed mechanism of loss of suction, details of damage to the pump and various modifications carried out to prevent recurrence of the problem. (author). 4 refs., 3 figs., 2 tabs

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. IV.4-1-IV.4-7.

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