论文部分内容阅读
利用RCC-M、FIS、FIM和RG1.99(2)模型,分别计算了300MW、600MW和1000MW三种国产A508-3钢的在AP1000工况下的辐照脆化性能;利用FIS模型的计算结果和NRC-RG1.99(2)模型提供的方法计算了调整参考温度。结果显示,600MW核压力容器材料的计算结果超出AP1000的标准要求,不适合用做AP1000的核压力容器,300MW和1000MW核压力容器材料的计算结果满足AP1000核压力容器的辐照脆化性能要求,适合用作AP1000的核压力容器。最后,提出了适当降低C、Ni等合金元素的含量、严格控制N/Al之比等方法以提高材料的抗辐照脆化性能、以实现AP1000核压力容器国产化的建议。
The radiation embrittlement properties of three Chinese-made A508-3 steels with 300MW, 600MW and 1000MW were analyzed by RCC-M, FIS, FIM and RG1.99 (2) model respectively under the AP1000 operating condition. By using the FIS model Results and methods provided by the NRC-RG1.99 (2) model calculated the adjusted reference temperature. The results show that the calculation results of 600MW nuclear pressure vessel material exceed the standard requirements of AP1000 and are not suitable for nuclear pressure vessel of AP1000. The calculation results of 300MW and 1000MW nuclear pressure vessel materials meet the irradiation embrittlement performance requirements of AP1000 nuclear pressure vessel, Suitable for use as a nuclear pressure vessel for the AP1000. Finally, some suggestions are put forward, such as reducing the content of alloying elements such as C and Ni, strictly controlling the ratio of N / Al and so on, in order to improve the anti-radiation embrittlement of the material and to realize the localization of AP1000 nuclear pressure vessel.