Nb稳定化奥氏体不锈钢在第四代核电领域的研究进展
陈胜虎, 谢昂, 杨彬彬, 刘涌涛, 陈思含, 赵明久, 姜海昌, 戎利建

Research Progress of the Niobium-Stabilized Austenitic Stainless Steels for Generation-IV Nuclear Reactors
CHEN Shenghu, XIE Ang, YANG Binbin, LIU Yongtao, CHEN Sihan, ZHAO Mingjiu, JIANG Haichang, RONG Lijian
表1 六种第四代反应堆系统的服役工况[6~10]
Table 1 Summary of the reactor core environments of the six Generation-IV reactor systems[6-10]
Reactor systemCoolantOutlet temperature / oCNeutron spectrum, maximum dose

Sodium fast reactor

Lead fast reactor

Gas fast reactor

Supercritical water reactor

Very high temperature reactor

Molten salt reactor

Sodium

Lead or lead-bismuth

Helium

Supercritical water

Helium

Molten salt

500-550

480-570

~850

510-625

900-1000

700-800

Fast, 150 dpa

Fast, 100 dpa

Fast, 90 dpa

Fast/thermal, 70 dpa

Thermal, 20 dpa

Thermal, 200 dpa