核聚变堆用<strong>W</strong>及其合金辐照损伤行为研究进展

核聚变堆用W及其合金辐照损伤行为研究进展

吴玉程^1,^2,³(

)

Research Progress in Irradiation Damage Behavior of Tungsten and Its Alloys for Nuclear Fusion Reactor

Yucheng WU^1,^2,³(

)

图6. W试样在同一辐照剂量(2.25×10²¹ m^-2)、不同温度(500、600和800 ℃)下辐照后，H泡密度与平均直径曲线图及气泡直径分布区间图^[47]

Fig.6. Hydrogen bubble density and average diameter (a) and bubble distribution at different diameters (b) for specimens irradiated at temperature 500 ℃, 600 ℃, 800 ℃ to a same dose of 2.25×10²¹ m^{-2 [47]}