Published 1992 | Version v1
Book

Thermal hydraulic analysis for the design of intermediate heat exchanger

  • 1. Nuclear Systems Division, Indira Gandhi Centre for Atomic Reseach, Kalpakkam (India)

Description

Prototype Fast Breeder Reactor (PFBR) is a sodium cooled reactor with 500MWe(1210MWt) capacity. Nuclear heat generated in the core is transferred to primary sodium flowing through the subassemblies. The hot primary sodium exchanges heat with secondary sodium through intermediate heat exchangers. A two dimensional analysis of the intermediate heat exchanger has clearly brought out the high values of radial temperature drop of primary and secondary sodium streams when the secondary flow is uniform. A solution of unequal secondary flow has proved to be an effective method to reduce the temperature drops leading to a safer design. (author). 7 refs., 5 figs

Additional details

Publishing Information

Publisher
Tata McGraw-Hill Publishing Co. Ltd.
Imprint Place
New Delhi (India)
Imprint Title
Heat and mass transfer : proceedings of the 11"t"h national heat and mass transfer conference [held at Madras during Dec 21-23, 1991]
Imprint Pagination
439 p.
Journal Page Range
p. 235-240.

Conference

Title
11. National heat and mass transfer conference.
Dates
21-23 Dec 1991.
Place
Madras (India).