首页> 外文期刊>Transactions of the Indian Institute of Metals >UTILITY AND PROCEDURE OF FRACTURE TOUGHNESS EVALUATION OF STEELS THROUGH MASTER CURVE APPROACH USING CHARPY IMPACT SPECIMENS
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UTILITY AND PROCEDURE OF FRACTURE TOUGHNESS EVALUATION OF STEELS THROUGH MASTER CURVE APPROACH USING CHARPY IMPACT SPECIMENS

机译:脆性冲击标本通过主曲线法进行钢断裂韧性评价的实用性和方法

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摘要

More often than not, fracture toughness data particularly in the transition region of pressure vessel ferritic steels are subjected to scatter. For designing structures operating in the transition region, an estimate of the lower bound fracture toughness scatter rather than lower bound fracture toughness would be desirable. Irradiation embrittlement being a key issue for the integrity assessment of operating nuclear pressure vessels, the assessment methodology needs to address this issue. This paper presents the origin and imposed limitations of fracture toughness data in transition region of pressure vessel ferritic steels vis-a-vis ASME Code reference toughness curve and the potentials of overcoming the limitation by using Master Curve Approach. The results reported in this paper formed a part of the round robin exercise entitled "Assuring Structural Integity of Reactor Pressure Vessels" initiated by International Atomic Energy Agency in 1996. The Master Curve Approach can be used for the evaluation of fracture toughness of all steels which exhibit a transition between brittle to ductile mode of fracture with increasing temperature, and to monitor the extent of embrittlement caused by metallurgical damage mechanisms.
机译:通常,断裂韧性数据(尤其是在压力容器铁素体钢的过渡区域中)会发生散射。为了设计在过渡区域中工作的结构,需要对下限断裂韧性的分散性进行评估,而不是对下限断裂韧性进行估算。辐射脆化是正在运行的核压力容器完整性评估的关键问题,评估方法需要解决这个问题。本文介绍了压力容器铁素体钢过渡区域相对于ASME规范参考韧性曲线的断裂韧性数据的起源和施加的局限性,以及使用主曲线法克服该局限性的潜力。本文报道的结果构成了由国际原子能机构于1996年发起的名为“确保反应堆压力容器的结构完整性”的循环练习的一部分。主曲线法可用于评估所有钢的断裂韧性,随着温度的升高,合金在脆性到延性断裂模式之间会发生转变,并监测由冶金破坏机制引起的脆化程度。

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