Published 1992 | Version v1
Book

Corrosion of zirconium base alloys - an overview

Creators

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

Description

History on the development of zirconium alloys for use as in-core material in water cooled reactors has shown the suitability of two types of alloys. In the first, studies based on Zr-Sn system have led to the emergence of two potential alloys zircaloy-2 and -4. In the other, extensive investigations on the Zr-Nb system have given rise again to two major alloys, namely Zr-1Nb and Zr-2.5Nb. The recent development of zirlo alloy with a composition Zr-lNb-lSn-0.1Fe is primarily considered for PWR application particularly for extended burn up levels. (author). 7 refs

Part of:
Proceedings [of the] symposium on zirconium alloys for reactor components

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre.
Imprint Place
Bombay (India)
Imprint Title
Proceedings [of the] symposium on zirconium alloys for reactor components
Imprint Pagination
738 p.
Journal Page Range
p. 148-154.

Conference

Title
symposium on zirconium alloys for reactor components.
Acronym
ZARC-91
Dates
12-13 Dec 1991.
Place
Bombay (India).

Optional Information