Zirconium alloys in nuclear technology

Krishnan, R. ; Asundi, M. K. (1981) Zirconium alloys in nuclear technology Sadhana (Academy Proceedings in Engineering Sciences), 4 (1). pp. 41-56. ISSN 0256-2499

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Official URL: http://www.ias.ac.in/j_archive/sadhana/4/1/41-56/v...

Related URL: http://dx.doi.org/10.1007/BF02843474

Abstract

This paper describes the historical development of zirconium and its alloys as structural materials for nuclear reactors. The various problems encountered in the early stages of the development of zircaloys and their performance in reactors operating presently are described in detail. The development of Zr-2.5 % Nb alloys for pressure tube applications is discussed. The paper concludes with a detailed discussion on the development potential of zirconium alloys for high temperature applications and a brief account of the work carried out at Trombay in this field.

Item Type:Article
Source:Copyright of this article belongs to Indian Academy of Sciences.
Keywords:Zirconium; Zirconium Alloys; Structural Materials; Nuclear Reactors; Corrosion; High Strength Alloys
ID Code:17431
Deposited On:16 Nov 2010 13:06
Last Modified:17 May 2016 02:04

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