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High-heat flux tests of tungsten divertor mock-ups with steady-state plasma and e-beam
Nuclear Materials and Energy ( IF 2.3 ) Pub Date : 2020-10-24 , DOI: 10.1016/j.nme.2020.100816
V.P. Budaev , S.D. Fedorovich , A.V. Dedov , A.V. Karpov , A.T. Komov , Yu.V. Martynenko , R.N. Giniyatulin , A.N. Makhankov , N.V. Litunovsky , A.P. Sliva , A.Yu. Marchenkov , D.N. Gerasimov , M.K. Gubkin , M.V. Lukashevsky , A.V. Zakharenkov , A.V. Lazukin , G.B. Vasiliev

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/m2 in the e-beam facility; and then (2) subsequent testing in the PLM plasma device with steady-state plasma loads of 0.5–1 MW/m2 and 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.



中文翻译:

带有稳态等离子体和电子束的钨分流器模型的高热通量测试

用稳态等离子体和电子束负载的组合对ITER分流板的样机进行测试:(1)在电子束设备中以高达40 MW / m 2的强大电子束负载进行热循环测试;然后(2)在稳态等离子负荷为0.5–1 MW / m 2的PLM等离子设备中进行后续测试和更多。此类测试模拟了ITER中分流板上的可变载荷。在PLM等离子设备上的实验中,用氦等离子体辐照钨样品,放电时间长达200分钟。结合稳态等离子体和热循环电子束负载进行的ITER级钨VM-P的测试导致了材料表面的腐蚀,破裂和纳米结构“起毛”结构的生长。验尸扫描电子显微镜和X射线分析表明,随机的纳米结构表面的结构元素尺寸小于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。此类测试的结果对于估算聚变反应堆(包括ITER,聚变中子源FNS和DEMO)中钨的腐蚀非常有意义。

更新日期:2020-10-29
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