低铜合金反应堆压力容器钢辐照脆化预测评估模型

Prediction Model on Irradiation Embitterment of Low Copper Alloy Reactor Pressure Vessel Steels

反应堆压力容器(RPV)材料辐照脆化预测评估对保证核反应堆安全运行、预防重大灾难性事故的发生具有重要意义。通过深入了解RPV材料辐照损伤机理和分析国外较为成熟的RPV辐照脆化预测模型,揭示了国外有关压力容器辐照脆化预测模型对低铜RPV辐照脆化预测的不足及其原因。在此基础上,发展和建立了适用于低铜RPV辐照脆化趋势的预测模型CIAE-2009。利用辐照性能数据对CIAE-2009模型进行了验证。结果表明,CIAE-2009对低铜含量RPV材料辐照脆化趋势预测具有较高的准确性和可靠性。

Accurate characterization of reductions in the fracture toughness of reactor pressure vessel （RPV） steels due to in-service neutron exposure is very important to the safe and reliable operation of nuclear power plants. The prediction model CIAE-2009 for irradiation embrittlement trend of low copper RPV steels was developed, and irradiation embrittlement data were used to verify the prediction model. The predicted fracture toughness trend indicates that the prediction model CIEA 2009 is correct and reliable.