Published 1977 | Version v1
Book

Operating experience with high temperature high pressure in-pile water loop

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

Description

Operating experience with high temperature-high pressure in-pile water loop at the CIRUS reactor, India, is reported. The pressurised water loop has been in use since 1972 and is being operated at 2600C, the mean operating temperature of RAPS-type reactors. The results of the study and the data collected are helpful in guiding the power reactor operations at RAPS. The materials of construction are zircaloy-2 as pressure tube (in-pile) and stainless steel (out-pile system). The loop is meant mainly for testing different types of power reactor fuel pins. Coolant chemistry is also taken up as an additional study since it helps to maintain chemical parameters at the optimum levels in power reactors where the primary coolant serves both as moderator and heat transport medium. (K.B.)

Additional details

Publishing Information

Publisher
Department of Atomic Energy.
Imprint Place
Bombay
Imprint Title
Symposium on operating experience of nuclear reactors and power plants [held during] February 7-9, 1977 [at] Bombay [Invited talks and contributed papers]
Journal Page Range
p. 393-397.

Conference

Title
Symposium on operating experience of nuclear reactors and power plants.
Dates
7 - 9 Feb 1977.
Place
Bombay, India.