M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: 1012
会議情報
1012 配管の熱疲労評価法の高度化に関する研究 : (4)支配因子に基づく合理的高サイクル熱疲労評価の枠組み(OS10-3 供用エネルギー機器の経年変化と健全性評価-熱疲労-)
三津谷 有貴笠原 直人
著者情報
会議録・要旨集 フリー

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抄録
High cycle thermal fatigue is one of postulated failure modes at the pipes of the cooling systems of the nuclear power plants. We examined this phenomenon and identified heat transfer coefficient, wall thickness and frequency of temperature fluctuation of fluid as dominant parameters. Thorough the fmite element analysis, we could obtain the curves to evaluate the effects of dominant parameters. And using these curves and theoretical equations, we proposed the frame work of evaluation method of high cycle thermal fatigue. As a result, the evaluation has found to be more accurate than current guideline of JSME and have proper safety margin against the actual phenomenon.
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© 2010 一般社団法人 日本機械学会
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