摘要
在核电项目中,与二代改进型压水堆堆内构件主体材料采用RCC-M系列牌号奥氏体不锈钢相比,AP1000反应堆堆内构件主体材料采用ASME系列牌号,堆内构件结构形式也存在较大差异。为有效利用国内制造厂的现有工艺手段和制造技术,避免重复投入,从ASME、RCC-M两种规范出发,通过两种堆型堆内构件主体材料的化学成分、力学性能、抗晶间腐蚀能力的比较分析,探讨AP1000堆内构件主体材料替代的可行性。
In nuclear power projects, compared with the second-generation improved pressurized water reactor which adopts the austenitie stainless steel of RCC-M series brand as the main material of core internals, AP1000 reactor adopts the austenitic stainless steel of ASME series. The construction of their core internals also differs significantly. To effectively utilize the existing techniques and manufacturing technologies of domestic manufacturers and avoid repeat investments, based on ASME and RCC-M standards, the feasibility of substituting the main material of AP1000 reactor core internals is discussed through comparing and analyzing the chemical compositions, mechanical properties, and intergranular corrosion resistance of the main internal materials between the two types of reactors.
出处
《发电设备》
2013年第1期40-43,共4页
Power Equipment
关键词
核电
堆内构件
晶间腐蚀
材料替代
nuclear power
reactor internal
intergranular corrosion
material substitute