Evaluation of the fracture research institute theoretical stress corrosion cracking model

Ernest D. Eason, Raj Pathania, Tetsuo Shoji

研究成果: Conference contribution

13 被引用数 (Scopus)

抄録

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.

本文言語English
ホスト出版物のタイトルProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
ページ145-154
ページ数10
出版ステータスPublished - 2005 12月 1
イベント12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
継続期間: 2005 8月 142005 8月 18

Other

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

ASJC Scopus subject areas

  • 工学(全般)

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