Published 1995 | Version v1
Book

A procedure for evaluating residual life of major components in light water reactors

  • 1. Hitachi, Ltd., Ibaraki (Japan)
  • 2. Babcock-Hitachi, Kure, Hiroshima (Japan)

Description

A computer program for evaluating residual life of major components in boiling water reactors is proposed. It divides the stress corrosion cracking process into two stages; a probabilistic crack generation stage and a deterministic crack propagation one. The minimum period of the crack generation stage is evaluated assuming an exponential distribution of the stage. The crack propagation rate is calculated by the slip-dissolution/film-rupture model. The neutron flux and fluence dependence of the neutron radiation effects on material properties was evaluated by using theoretical models of radiation damage. The computer program works on an engineering work station. Evaluated results are displayed as a map of the residual life, or as graphs of crack length evolution

Additional details

Publishing Information

Publisher
NACE International.
Imprint Place
Houston, TX (United States)
ISBN
1-877914-95-9
Imprint Title
Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2
Imprint Pagination
620 p.
Journal Page Range
p. 959-969.

Conference

Title
water reactors.
Acronym
7. NACE international symposium on environmental degradation of materials in nuclear power plants
Dates
6-10 Aug 1995.
Place
Breckenridge, CO (United States).

Optional Information

Secondary number(s)
CONF-950816--.