Development of a new irradiation-embrittlement prediction model for reactor pressure-vessel steels  

作　　者：Qi-Bao Chu Lu Sun Zhen-Feng Tong Qing Wang 

机构地区：[1]Ministry of Ecology and Environment,Nuclear and Radiation Safety Center,Beijing 100082,China [2]School of Nuclear Science and Engineering,North China Electric Power University,Beijing 102206,China

出　　处：《Nuclear Science and Techniques》2024年第11期182-192,共11页核技术（英文）

基　　金：supported by the National Key R&D Program of China (No. 2019YFB1900901);the Fundamental Research Funds for the Central Universities (No. 2021MS032)

摘　　要：Predicting the transition-temperature shift(TTS)induced by neutron irradiation in reactor pressure-vessel(RPV)steels is important for the evaluation and extension of nuclear power-plant lifetimes.Current prediction models may fail to properly describe the embrittlement trend curves of Chinese domestic RPV steels with relatively low Cu content.Based on the screened surveillance data of Chinese domestic and similar international RPV steels,we have developed a new fluencedependent model for predicting the irradiation-embrittlement trend.The fast neutron fluence(E>1 MeV)exhibited the highest correlation coefficient with the measured TTS data;thus,it is a crucial parameter in the prediction model.The chemical composition has little relevance to the TTS residual calculated by the fluence-dependent model.The results show that the newly developed model with a simple power-law functional form of the neutron fluence is suitable for predicting the irradiation-embrittlement trend of Chinese domestic RPVs,regardless of the effect of the chemical composition.

关 键 词：Reactor pressure vessel steel Transition temperature shift Irradiation embrittlement Embrittlement trend curve Prediction model 

分 类 号：TL351.6[核科学技术—核技术及应用]