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(
)
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Research Progress in Irradiation Damage Behavior of Tungsten and Its Alloys for Nuclear Fusion Reactor
Yucheng WU1,2,3()
)
图9. 未损伤、300 K下0.2 dpa辐照剂量和1240 K下0.2 dpa辐照剂量试样的TDS图谱[
Fig.9. TDS emission spectra for undamaged sample (black dashed line), damaged to 0.2 dpa at 300 K (blue line) and at 1240 K (red line). Data obtained with a TDS temperature ramp rate of 0.5 K/s[
