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Alloy 690 증기발생기 전열관 크리프 손상거동 예측
문성인(Seongin Moon),김종민(Jong-Min Kim),권준엽(Joon-Yeop Kwon),이봉상(Bong-Sang Lee),김민철(Min-Chul Kim) 대한기계학회 2021 대한기계학회 춘추학술대회 Vol.2021 No.11
Steam generator tubes in nuclear power plants could undergo rapid changes in pressure and temperature, and the creep damage accumulates within only several hours or days. To estimate the creep behavior of structures constant stress creep curve is needed but many creep test data are obtained under constant load. Therefore, creep rupture behavior of structures cannot be accurately simulated. This study proposes a novel methodology to obtain the creep curve under constant stress using a modified θ projection method that considers the increase in true stress during creep deformation in a constant load creep test. The methodology is validated using finite element analysis. Also, a creep-strain model for Alloy 690 is proposed, ant then it is applied to evaluate the creep rupture behavior of SG tubes.
문성인(Seong-In moon),김민수(Min-Soo Kim),윤성진(Sung-Jin Yoon),전재욱(Jae-Wook Jeon) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
Rubber components have been widely used in automotive industry as anti-vibration components for many years. These subjected to fluctuating loads, often fail due to the nucleation and growth of defects or cracks. In order to prevent such failures, it is necessary to understand the fatigue failure mechanism for rubber materials and to evaluate the fatigue life for rubber components. The objective of this study is to evaluate the fatigue failure mode and to select the applicable fatigue damage parameter for vulcanized rubber components. In order to investigate the applicability of the commonly used damage parameters, fatigue tests and corresponding finite element analyses and fatigue analyses for automotive rubber components were carried out. The fatigue failure mode was evaluated and the applicability of the fatigue damage parameters was verified. Thereby, strain energy density was proposed as the fatigue damage parameter for rubber components.
문성인(Seong-In Moon),장윤석(Yoon-Suk Chang),김영진(Young-Jin Kim),이진호(Jin-Ho Lee),송명호(Myung-Ho Song),최영환(Young-Hwan Choi),황성식(Seong-Sik Hwang) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.8
The 40% of wall thickness criterion, which is generally used for the plugging of steam generator tubes, is applied only to a single crack. In the previous study, a total number of 10 local failure prediction models were introduced to estimate the coalescence load of two collinear through-wall cracks and the reaction force model and plastic zone contact model were selected as optimum ones. The objective of this study is to estimate the coalescence load of two collinear through-wall cracks in steam generator tube by using the optimum local failure prediction models. In order to investigate the applicability of the optimum local failure prediction models, a series of plastic collapse tests and corresponding finite element analyses for two collinear through-wall cracks in steam generator tube were carried out. Thereby, the applicability of the optimum local failure prediction models was verified and finally a coalescence evaluation diagram which can be used to determine whether the adjacent cracks detected by NDE coalesce or not was developed.