Current status and future of IASCC research

Tetsuo Shoji, Shun Ichi Suzuki, K. S. Raja

Research output: Contribution to journalArticle

16 Citations (Scopus)

Abstract

Irradiation Assisted Stress Corrosion Cracking (IASCC) is a complex phenomenon occurring in structural components of nuclear reactor cores. It assumes a greater importance for the selection of suitable materials for fusion wall applications. This paper reviews the available data on the effect of irradiation damage on the environmental cracking behavior of austenitic and ferritic steels. It is shown that the changes in microstructures of the materials and the environmental changes due to irradiation have been widely investigated. However, further research is required to study the behavior of initiation and propagation of stress corrosion cracks, considering these as two separate events, for austenitic and ferritic steels under irradiation.

Original languageEnglish
Pages (from-to)241-251
Number of pages11
JournalJournal of Nuclear Materials
Volume258-263
Issue numberPART 1 A
DOIs
Publication statusPublished - 1998 Oct

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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    Shoji, T., Suzuki, S. I., & Raja, K. S. (1998). Current status and future of IASCC research. Journal of Nuclear Materials, 258-263(PART 1 A), 241-251. https://doi.org/10.1016/S0022-3115(98)00304-3