等価応力振幅を用いた配管熱疲労評価法による評価結果の比較


英字タイトル:
Comparison of Evaluation Results of Piping Thermal Fatigue EvaluationMethod based on Equivalent Stress Amplitude
著者:
鈴木 隆史 Takafumi SUZUKI 笠原 直人 Naoto KASAHARA
発刊日:
公開日:
カテゴリ: 第9回
キーワードタグ:

概要

In recent years, reports have increased about failure cases caused by high cycle thermal fatigue both at light water reactors and fast breeder reactors. One of the reasons of the cases is a turbulent mixing at a Tee -junction, where hot and cold temperature fluids are mixed, in a coolant system. In order to prevent thermal fatigue failures at Tee-junctions, The Japan Society of Mechanical Engineers published the guideline which is an evaluation method of high cycle thermal fatigue damage at nuclear pipes. In order to justify safety margin and make the procedure of the guideline concise, this paper proposes a new evaluation method of therm al fatigue damage with use of the “equivalent stress amplitude.” Because this new method makes procedure of evaluation clear and concise, it will contribute to improving the guideline for thermal fatigue evaluation,


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