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用慢正电子束研究H/He中性束辐照W-ZrC合金中的缺陷演化
Defect Evolution in H/He Neutral Beam Irradiated W-ZrC Alloy Using Positron Annihilation Spectroscopy
【摘要】 利用GLADIS中性粒子束辐照设备对W-ZrC (W-0.5%ZrC,质量分数)合金进行纯H中性束辐照、H+6%He (原子分数)中性束辐照。采用Doppler展宽慢正电子束分析(DB-SPBA)和SEM表征样品的空位型缺陷和表面形貌。在相同纯H中性束辐照功率与注量下,Doppler展宽结果表明,辐照表面温度为850℃时,样品中缺陷类型主要为空位与H之比较大的H-V复合体;1000℃的样品不存在缺陷损伤层,这主要是由于缺陷在高温下进行了恢复。SEM结果表明,辐照表面温度为1000℃的样品比850℃的样品表面光滑,表面损伤得到恢复。在相同H+6%He中性束辐照功率与注量下,辐照表面温度为800℃的样品相比700℃的样品,S参数更大,表明辐照表面温度为800℃时,空位型缺陷迁移合并更为明显,空位型缺陷体积更大,样品中的缺陷损伤层更宽,损伤更为严重。
【Abstract】 Plasma facing materials(PFMs) in future magnetic fusion devices will face various challenges, such as 14.1 MeV neutron and transmutation gas irradiation at high temperatures. W has been considered as one of the most effective candidates for a PFM in recent years. However, pure W exhibits some drawbacks that limit its applications. Conversely, W-ZrC(W-0.5%ZrC, mass fraction) alloy demonstrates excellent performance, such as a relatively low ductile-brittle transition temperature(DBTT), high ductility, and high strength, which will be particularly useful in future fusion reactors. In this work, the Doppler-broadening slow positron beam analysis(DB-SPBA) and SEM were used to characterize the W-ZrC alloy, which had been irradiated by pure H neutral beam or H+6%He(atomic fraction) neutral beam. Inthe DB-SPBA, parameters S and W were used to characterize the open volume defects in the samples.Under the pure H neutral beam irradiation, the defects were mainly H-V complexes with a large ratio of vacancy to H in the sample at the surface temperature of 850 oC. When the surface temperature of the irradiated sample was 1000 oC, there was only one kind of vacancy-type defect without any defect damage layer due to the recovery of defect damage in the sample. The surface morphology was smooth and flat at the irradiated sample surface temperature of 1000 oC, and the most of pinhole damage structures disappeared compared to the surface temperature of 850 oC. The S value in the sample subjected to the H+6%He neutral beam irradiation at the surface temperature of 800 oC was larger than that at 700 oC because of the increasing vacancy-type defect volume, and defect types were more complex in the 800 oC sample. The defect damage layer in the 800 oC sample was wider than that in the 700 oC sample. Both the700 oC and 800 oC samples presented more than one type of defects, but the sample surface damage was significantly more serious at 800 oC.
- 【文献出处】 金属学报 ,Acta Metallurgica Sinica , 编辑部邮箱 ,2021年01期
- 【分类号】TG146.411
- 【被引频次】1
- 【下载频次】101