Post-irradiation SCC investigations on highly-irradiated core internals component materials

Aki Toivonen, Pertti Aaltonen, Wade Karlsen, Ulla Ehrnstén, Jean-Paul Massoud, Jean-Marie Boursier

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    After the shutdown of the Chooz A Power Plant, core internals material samples have been made available, particularly a highly irradiated AISI 304 core baffle corner material with a fluence corresponding to 20 years of operation of a PWR. SCC tests (Constant Load Tests and Slow Strain Rate Tensile Tests) have been performed and will be presented in this paper as well as some complementary fractographic investigations. The effects of stress level, initial loading rate, test temperature and test environment will be discussed. Following these results a full time to failure versus stress curve can be proposed for this irradiated material. Intergranular cracking was observed after constant load and SSRT tests at 340°C in simulated PWR water but also in argon, although to a lesser extent. Complementary investigations to clarify the mechanical behaviour of the irradiated steel were also performed and the results will be discussed.
    Original languageEnglish
    Title of host publication6th International Symposium on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs: Proceedings
    Pages567-579
    Volume1
    Publication statusPublished - 2006
    MoE publication typeNot Eligible
    EventFontevraud 6 International Symposium: Contribution of materials investigations to improve the safety and performance of LWRs - Fontevraud Royal Abbey, Fontevraud-l'Abbaye, France
    Duration: 18 Sep 200622 Sep 2006

    Conference

    ConferenceFontevraud 6 International Symposium
    CountryFrance
    CityFontevraud-l'Abbaye
    Period18/09/0622/09/06

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