M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: OS0808
会議情報
OS0808 原子炉圧力容器破壊評価における拘束効果に関する解析的検討
高見澤 悠勝山 仁哉山口 義仁西山 裕孝鬼沢 邦雄
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会議録・要旨集 フリー

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For the integrity assessment of reactor pressure vessel (RPV) under pressurized thermal shock (PTS) condition is the most important event. The integrity of RPV is assessed by comparing stress intensity factor on a crack tip and the fracture toughness obtained from surveillance tests. The miniature compact tension (CT) specimen machined from surveillance specimens is expected to directly evaluate the fracture toughness. However, it has been recognized that a constraint effect in CT specimens is greater than that of the postulated crack in RPV, and it causes a conservative evaluation. Therefore, clarification of the conservativeness is required for more reasonable evaluation. In order to examine the mechanical factors related to the constraint effect of the crack, T stress, Q factor, and Weibull stress are useful. In this study, 3D elastic plastic finite element analyses were performed for CT specimens with different size and RPV models, to evaluate the above mechanical factors. From the analysis results, a larger constraint effect for CT specimens is observed than that for the postulated crack for RPV. We discussed on the conservativeness of the current structural integrity assessment methodology.
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