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Report No.
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New evaluation method of material degradation considering synergistic effects of radiation damage

Miwa, Yukio; Kaji, Yoshiyuki  ; Okubo, Nariaki   ; Kondo, Keietsu  ; Tsukada, Takashi 

In core structural materials of next generation reactors, materials' degradation behavior by neutron irradiation damage and thermal (cyclic) stress should be considered with fair accuracy in design process (including maintenance and repair plans), because the materials are used under higher temperature gradients and higher neutron flux fields than those in the present light water reactors. In the current experiential design rules, service lives of core structural components were determined by the materials degradation such as the increase of ductile-to-brittle transition temperature after post irradiation examination data. However, other materials degradations such as irradiation-assisted stress corrosion cracking (IASCC) should be considered reasonably in the design process of the next generation reactors, because of the anticipation of the beneficial effects by synergistics of these radiation damage such as radiation hardening, local chemical composition change, swelling and radiation creep. To predict material failure by IASCC with reasonable accuracy, in this study, each material degradation phenomenon with different dose dependence was modeled with consideration of radiation induced stress relaxation. The models were integrated to simulate the failure behavior for the reactor operation period. In this paper, the models obtained by ion-irradiation experiments were presented, and the concept of new evaluation method and the programming code for the failure simulation were outlined.

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