Studying of in-vessel component materials under high power electron beam and steady-state plasma loads

被引：2

作者：

Budaev, Viacheslav Petrovich ^{[1
,2
]}

Fedorovich, Sergey ^{[1
]}

Dedov, Alexey ^{[1
]}

Martynenko, Yuri ^{[1
,2
]}

Karpov, Alexey ^{[1
,2
]}

Lukashevsky, Mikhail ^{[1
]}

Gubkin, Mikhail ^{[1
]}

Lubenchenko, Alexander ^{[1
]}

Komov, Alexander ^{[1
]}

Dragunov, Victor ^{[1
]}

Sliva, Andrey ^{[1
]}

Marchenkov, Artem ^{[1
]}

Zakharenkov, Alexander ^{[1
]}

Kavyrshin, Dmitry ^{[1
]}

Vasilyev, Grigory ^{[1
]}

Quang, V. Tran ^{[1
]}

Rogozin, Konstantin ^{[1
]}

Konkov, Alexey ^{[1
]}

机构：

[1] Natl Res Univ MPEI, Moscow, Russia

[2] Kurchatov Inst, Natl Res Ctr, Moscow, Russia

来源：

FUSION ENGINEERING AND DESIGN | 2021年 / 167卷

关键词：

Plasma irradiation; e-beam test; Plasma-facing materials; Tungsten; Fusion reactor; HEAT-FLUX; ITER; SURFACE;

D O I：

10.1016/j.fusengdes.2021.112335

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Combined tests of tungsten mock-ups with thermocyclic test in the electron beam facility with the load up to 50 MW/m(2) and subsequent irradiation with steady-state plasma load up to 1 MW/m(2) in PLM device have been carried out to simulate a material degradation under loads expected in a fusion reactor. Cracks of 1-5 microns and more have been formed on the surface of the tungsten during e-beam test. Melted layer observed in the area of e-beam hot spot load. Plasma load led to a formation of nanostructured layers on the surface.

引用

页数：5

共 32 条

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