Tests of tungsten divertor mock-ups with plasma and e-beam high-heat fluxes

被引:0
作者
Budaev, V. P. [1 ,2 ]
Dedov, A. V. [1 ]
Komov, A. T. [1 ]
Varava, A. N. [1 ]
Frik, P. G. [1 ,3 ]
Fedorovich, S. D. [1 ]
Giniyatulin, R. N. [2 ]
Makhankov, A. N.
Litunovsky, N. V. [2 ]
Zakharenkov, A. V. [1 ]
Sviridov, E. V. [1 ]
Tupotilov, I. A. [1 ]
Chang, B. L. H. [1 ]
机构
[1] Natl Res Univ MPEI, Moscow, Russia
[2] Natl Res Ctr, Kurchatov Inst, Moscow, Russia
[3] Inst Continuous Media Mech, Perm, Russia
来源
XLVI ZVENIGOROD INTERNATIONAL CONFERENCE ON PLASMA PHYSICS AND CONTROLLED FUSION | 2019年 / 1383卷
基金
俄罗斯科学基金会;
关键词
SURFACE; ITER;
D O I
10.1088/1742-6596/1383/1/012017
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The tungsten divertor mock-ups were tested with high-heat fluxes in the e-beam facility and in the plasma device. The water-cooled mock-ups are tested with the combination of plasma and e-beam loads: (1) thermocyclic tests with the high-power electron beam load ranging from 5 to 40 MW/m(2) and then (2) tests in the PLM plasma device with stationary plasma loads of up to 5 MW/m(2). Such two tests are performed together for the first time. They simulate the variable loads onto the divertor plates, which can occur in the ITER during stationary discharges with transient ELM events. The duration of helium plasma discharges in the PLM amounted to 200 minutes. The temperature of the test targets heating amounted to 1000 degrees C and more.
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页数:4
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