High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam
High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam
复制标题
使用稳态等离子体和电子束对钨偏滤器模型进行高热通量测试
DOI：
10.1016/j.nme.2020.100816
复制
发表时间：
2020
影响因子：
2.6
通讯作者：
G. Vasiliev
中科院分区：
文献类型：
--
作者：
V. Budaev;S. Fedorovich;A. Dedov;A. Karpov;A. Komov;Y. Martynenko;R. Giniyatulin;A. Makhankov;N. Litunovsky;A. Sliva;A. Marchenkov;D. Gerasimov;M. Gubkin;M. Lukashevsky;A. V. Zakharenkov;A. Lazukin;G. Vasiliev
ITER偏滤器板的实体模型在稳态等离子体和电子束载荷的组合下进行了测试：（1）在电子束设施中使用高达40 MW/m2的强电子束载荷进行热循环测试;（2）随后在PLM等离子体装置中使用0.5-1 MW/m2或更高的稳态等离子体载荷进行测试。这种试验模拟了ITER偏滤器板上的可变载荷。在PLM等离子体装置上进行氦等离子体辐照钨样品的实验，放电持续时间长达200 min。ITER级钨VM-P的稳态等离子体和热循环电子束负载相结合的测试导致材料表面的侵蚀、开裂和纳米结构“绒毛”结构生长。死后扫描电子显微镜和X-射线分析显示，一个随机的纳米结构的表面与结构元素的尺寸小于100 nm。观察到具有“绒毛”型结构和高孔隙率的纳米结构表面的生长。这些试验结果对估算聚变堆中钨的侵蚀有重要意义，包括ITER、聚变中子源FNS和DEMO。
Mock-ups of the ITER divertor plate are tested with the combination of steady-state plasma and e-beam loads: (1) thermocyclic tests with powerful electron beam load of up to 40 MW/m2in the e-beam facility; and then (2) subsequent testing in the PLM plasma device with steady-state plasma loads of 0.5–1 MW/m2and more. Such tests simulate the variable load on divertor plates in the ITER. Tungsten samples are irradiated with helium plasma in experiments on the PLM plasma device with discharge duration of up to 200 min. The tests of ITER-grade tungstenVM-P with the combination of steady-state plasma and thermocyclic e-beam loads led to erosion, cracking, and nanostructured “fuzz” structure growth on the material surface. Post-mortem scanning electron microscopy and X-ray analysis revealed a stochastic nanostructured surface with dimension of structural elements less than 100 nm. The growth of a nanostructured surface with a “fuzz”-type structure and high porosity is observed. The results of such tests are of interest to estimate the erosion of tungsten in fusion reactors, including ITER, fusion neutron source FNS and DEMO.