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首页> 外文期刊>Journal of Engineering for Gas Turbines and Power >Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels
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Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

机译：日本反应堆压力容器钢脆性相关新方法的特点

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摘要

Neutron irradiation embrittlement of reactor pressure vessel steels is an important aging issue for the long-term operation of light water reactors. A new embrittlement correlation method was developed by Central Research Institute of Electric Power Industry and the Japanese electric utilities in 2007. This method is primarily based on the fundamental understandings on the embrittlement mechanisms, i.e., microstructural changes were modeled by the mathematical form of rate equations, and the predicted microstructural changes were further correlated with the mechanical property changes in transition temperature region. The coefficients of the rate equations were optimized using the Japanese surveillance data of RPV embrittlement. This method was adopted as the revision of the Japanese code, JEAC4201-2007, in 2007. In this paper, after a brief explanation on the new correlation method, the predictions of the new method will be investigated through comparisons with the previous correlation, JEAC4201-2004, and the U.S. surveillance data in order to identify the characteristics of the new method.
机译：反应堆压力容器钢的中子辐照脆化是轻水反应堆长期运行的重要老化问题。日本电力工业中央研究院和日本电力公司于2007年开发了一种新的脆化相关方法。该方法主要基于对脆化机理的基本理解，即通过速率方程的数学形式对微结构变化进行建模。 ，并且预测的微结构变化与转变温度区域的力学性能变化进一步相关。使用RPV脆化的日本监测数据优化了速率方程的系数。该方法于2007年作为日语代码JEAC4201-2007的修订版采用。在对新的相关方法进行简要说明之后，将通过与以前的相关方法JEAC4201进行比较来研究新方法的预测。 -2004年，以及美国监视数据以识别新方法的特征。

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