Published November 2006 | Version v1
Book

Boiling water reactor pipe cracking: prediction, detection and life extension

Creators

  • 1. Atomic Fuels Div., Bhabha Atomic Research Centre, Mumbai (India)

Description

In boiling water reactors (BWRs), austenitic stainless steels (grades AISI 304 and 316) have been used for various piping systems. The welding of these pipes provides the sensitised microstructure as well as residual stress whereas high temperature oxygenated water due to radiolysis provides the specific environment for intergranular stress corrosion cracking (IGSCC). After initial IGSCC incidents in BWR pipes in 1974, extensive investigations have been carried out in the last two decades to develop various remedial measures. This paper reviews the various methods developed for prediction, detection and life extension of IGSCC affected BWR pipes. (author)

Part of:
Proceedings of national conference on ageing management of structures, systems and components. V. 1: invited talks

Additional details

Publishing Information

Publisher
Nuclear Power Corporation of India Ltd.
Imprint Place
Mumbai (India)
ISBN
81-88513-23-7
Imprint Title
Proceedings of national conference on ageing management of structures, systems and components. V. 1: invited talks
Imprint Pagination
227 p.
Journal Page Range
p. 146-155

Conference

Title
national conference on ageing management of structures, systems and components; NRT - 2: 2. national conference on reactor technology
Acronym
NCAM - 2004
Dates
15-17 Dec 2004
Place
Mumbai (India)

Optional Information

Notes
14 refs., 8 figs., 3 tabs.