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4. W、W-3%Re和W-5%Re试样fuzz结构截面图及3组试样的fuzz厚度分布图以及对应的SEM像[
Fig.4. Cross section of fuzz in W (a), W-3%Re (b) and W-5%Re (c) and plot of the variation of fuzz depth with rhenium concentration (d), and SEM images of fuzz in W (e), W-3%Re (f), W-5%Re (g) for samples exposed for 400 s at a flux of 1024 m-2·s-1 and temperature of 1400 ℃ in Pilot PSI[
