Qualification of Boron Carbide Ceramics for Use in ITER Ports

被引:19
作者
Shoshin, Andrey [1 ]
Burdakov, Alexander [1 ,2 ]
Ivantsivskiy, Maxim [1 ,2 ]
Polosatkin, Sergey [1 ,2 ]
Klimenko, Maria [1 ,2 ]
Semenov, Alexey [1 ,2 ]
Taskaev, Sergey [1 ]
Kasatov, Dmitrii [1 ]
Shchudlo, Ivan [1 ]
Makarov, Alexander [1 ]
Davydov, Nikolay [3 ]
机构
[1] Russian Acad Sci, Budker Inst Nucl Phys, Siberian Branch, Novosibirsk 630090, Russia
[2] Novosibirsk State Tech Univ, Phys & Tech Dept, Novosibirsk 630092, Russia
[3] Novosibirsk State Univ, Phys Dept, Novosibirsk 630090, Russia
基金
俄罗斯科学基金会;
关键词
Ceramics; Boron; Temperature measurement; Neutrons; Nuclear physics; Current measurement; Boron carbide ceramic material properties; ITER port mechanical engineering; TUNGSTEN; RAY;
D O I
10.1109/TPS.2019.2937605
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
Boron carbide has been proposed for the neutron protection of equipment in the ITER diagnostic ports and for reducing the dose to maintenance personnel. The chemical composition, vacuum, and thermal properties of ceramics of boron carbide were studied. It is demonstrated that the outgassing rate of ceramics meets the requirements of the ITER Vacuum Handbook. Calculation of the total gas emission from the ITER equatorial port #11 is carried out. The contact thermal conductivity at the boundary between ceramics and bronze is measured. Manganese content is determined by the method of activation analysis in ceramics. It is shown that sintered and hot-pressed boron carbide ceramics can be used in the ITER diagnostic ports.
引用
收藏
页码:1474 / 1478
页数:5
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