The SSC RIAR high-flux research reactors: experience and possibilities of testing materials and mock-ups for fusion

被引:1
|
作者
Melder, RR [1 ]
Chakin, VP [1 ]
Pokrovsky, AS [1 ]
Shchuchkin, AN [1 ]
机构
[1] RIAR, RF, SSC, FSUE, Dimitrovgrad 433510, Ulyanovsk Regio, Russia
关键词
high-flux reactor; mock-ups; divertor plate; copper alloys; beryllium; swelling; capsule; irradiation; radiation damage; temperature; neutron fluence;
D O I
10.1016/S0920-3796(03)00392-2
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
A significant part of the operation parameters of the high power loaded elements of a fusion reactor can be reproduced in a high-flux fission reactors with considerable neutron spectrum hardness. This paper presents basic characteristics of the SM and BOR-60 high-flux reactors that are being currently under operation at RIAR as well as some examples of their usage for scientific programs performed for validation of radiation resistance of structural materials and mock-ups of some fusion reactor units. In particular, at present the program on the examination of developed copper alloys, welded and brazed joints of copper//steel type after irradiation in the SM reactor is performed for validation of the ITER divertor plate. Beryllium of various grades is examined for DEMO reactor blanket. A unique experiment was performed on simulation of expected operation conditions of the ITER divertor plate using mock-ups under fission reactor conditions. (C) 2003 Elsevier B.V. All rights reserved.
引用
收藏
页码:409 / 417
页数:9
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