Evaluation of the fracture research institute theoretical stress corrosion cracking model

Ernest D. Eason, Raj Pathania, Tetsuo Shoji

Research output: Chapter in Book/Report/Conference proceedingConference contribution

12 Citations (Scopus)

Abstract

A model of stress corrosion cracking (SCC) of Type 304 stainless steel in Boiling Water Reactor environments has been developed by the Fracture Research Institute (FRI) of Tohoku University, incorporating simple models of electrochemistry, material properties, and mechanics of crack growth. The model is an extension of the well-known Ford & Andresen model, adding the effect on local strain rate of a growing crack in a hardening material. This paper is a computational evaluation of the FRI model. Simulated crack growth rates (CGR) from the FRI model are compared with well-controlled laboratory data on the Type 304 heat tested in a recent international round robin study, including constant load and constant K tests in various water environments. Reasonable agreement is obtained between the model simulations and experimental data. The sensitivity of the results to key input parameters is evaluated and methods of estimating the key non-measurable parameter are presented.

Original languageEnglish
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages145-154
Number of pages10
Publication statusPublished - 2005 Dec 1
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: 2005 Aug 142005 Aug 18

Other

Other12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
CountryUnited States
CitySalt Lake City, UT
Period05/8/1405/8/18

Keywords

  • BWR
  • SCC
  • Stainless Steel
  • Stress Corrosion Cracking Model

ASJC Scopus subject areas

  • Engineering(all)

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