Fusion safety studies in Russia from 1996 to 2000

被引:9
作者
Kolbasov, BN
Biruykov, AY
Davydov, DA
Guseva, MI
Khripunov, BI
Korshunov, SN
Martynenko, YV
Romanov, PV
Vasiliev, VI
机构
[1] Russian Res Ctr Kurchatov Inst, Nucl Fus Inst, Moscow 123182, Russia
[2] AA Bochvar Inorgan Mat Res Inst, VNIINM, SSC RF AA, Moscow, Russia
[3] Troitsk Inst Innovat & Thermonucl Invest, TRINITI, Troitsk, Moscow Region, Russia
关键词
fusion safety; co-deposited layer; dust characterization; hydrogen inventory; beryllium-steam/air interaction;
D O I
10.1016/S0920-3796(00)00566-4
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
The paper is a review of results of some fusion safety studies performed in Russia during 1996-2000 (after the 6th IAEA Technical Committee Meeting on 'Developments in Fusion Safety'). In particular, changes of hydrogen isotope inventory in co-deposited layers on tungsten and graphite under simulation of normal tokamak operation and plasma disruptions are reported. Size distribution of graphite and W-Be-dust under the experiments at issue revealed two maximums. Erosion products were collected within tokamak T-IO. Their microstructure and chemical composition were studied and are reported in the paper. Chemical interaction of beryllium powder with steam (in temperature range of 400-600 degreesC) and air (at 500-1000 degreesC) was investigated. Mathematical models describing it were developed. Chemical interaction of Be-powder with carbon was studied too. A dependence of beryllium carbide layer thickness growth versus time at 950 degreesC was found on the basis of the experiments. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:451 / 464
页数:14
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