NB/T 20007.50-2018.Stainless steel for pressurized water reactor nuclear power plants-Part 50: Austenitic stainless steel forgings for nuclear safetyrelated components.NB/T 20007.50规定了压水堆核电厂安全级设备用奥氏体不锈钢锻件的制造、检验和验收等要求。
NB/T 20007.50适用于压水堆核电厂反应堆压力容器、蒸汽发生器、稳压器、安注箱、堆内构件、堆芯补水箱、正常余热排出热交换器、非能动余热排出热交换器、...................
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