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The effect of light water reactor environments on the fatigue crack growth rate in reactor pressure vessel steels

  • Kari Törrönen
  • , William Cullen
  • VTT (former employee or external)
  • Materials Engineering Associates Inc.

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleScientificpeer-review

Abstract

This paper presents an overview of the effect of light-water reactor environments on the fatigue crack growth rate in reactor pressure vessel steels. The effect of different variables known to influence the environmental assistance—stress intensity range, load ratio, frequency, temperature, water chemistry, and irradiation—is described. The fractographic phenomena and mechanisms of fatigue crack propagation associated with environmental influence is emphasized. An analytical approach for predicting the crack growth rates based on the hydrogen embrittlement model is described. Finally, a discussion of the effect of different transients occurring in the nuclear reactors on the crack growth rate predictions is presented.
Original languageEnglish
Title of host publicationLow-cyclic fatigue and life prediction
EditorsC. Amzallag, B.N. Leis, P. Rabbe
Place of PublicationPhiladelphia
PublisherAmerican Society for Testing and Materials (ASTM)
Pages460-481
ISBN (Electronic)978-0-8031-4835-2
ISBN (Print)978-0-8031-0713-7
DOIs
Publication statusPublished - 1982
MoE publication typeA3 Part of a book or another research book

Publication series

SeriesASTM Selected Technical Papers
Volume770

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