Investigation of irradiation induced inter-granular stress corrosion cracking susceptibility on austenitic stainless steels for PWR by simulated radiation induced segregation materials

Toshio Yonezawa, Koji Fujimoto, Hiroshi Kanasaki, Toshihiko Iwamura, Shizuo Nakada, Kazuhide Ajiki, Sigeru Urata

    Research output: Contribution to journalArticlepeer-review

    2 Citations (Scopus)

    Abstract

    An Irradiation Assisted Stress Corrosion Cracking (IASCC) has not been found in Pressurized Water Reactors (PWRs). However, the authors have investigated on the possibility of IASCC so as to be able to estimate the degradation of PWR plants up to the end of their lifetime. In this study, the authors melted the test alloys whose bulk compositions simulated the grain boundary compositions of irradiated Type 304 and Type 316 CW stainless steels. Low chromium, high nickel and silicon (12%Cr-28%Ni-3%Si) steel showed high susceptibility to PWSCC (Primary Water Stress Corrosion Cracking) by SSRT (Slow Strain Rate Tensile) test in simulated PWR primary water. PWSCC susceptibility of the test steels increases with a decrease of chromium content and a increase of nickel and silicon contents. The aged test steel included coherent M23C6 carbides with matrices at the grain boundaries showed low PWSCC susceptibility. This tendency is in very good agreement with that of the PWSCC susceptibility of nickel based alloys X-750 and 690. From these results, if there is the possibility of IASCC for austenitic stainless steels in PWRs, in the future, the IASCC shall be caused by the PWSCC as a result of irradiation induced grain boundary segregation.

    Original languageEnglish
    Pages (from-to)437-444
    Number of pages8
    JournalZairyo to Kankyo/ Corrosion Engineering
    Volume49
    Issue number7
    DOIs
    Publication statusPublished - 2000

    ASJC Scopus subject areas

    • Surfaces, Coatings and Films
    • Metals and Alloys
    • Electrochemistry
    • Materials Chemistry

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