Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports

被引:8
作者
Juarez, R. [1 ]
Guirao, J. [2 ]
Pampin, R. [3 ]
Loughlin, M. [2 ]
Polunovskiy, E. [2 ]
Le Tonqueze, Y. [2 ]
Bertalot, L. [2 ]
Kolsek, A. [1 ]
Ogando, F. [1 ]
Udintsev, V. [2 ]
Walsh, M. [2 ]
机构
[1] ETSII UNED, Dept Ingn Energet, Calle Juan del Rosal 12, Madrid 28040, Spain
[2] ITER Org, 13115 Route Vinon Verdon, St Paul Les Durance, France
[3] Fus Energy F4E, Torres Diagonal Litoral B3, Josep Pla 2, Barcelona 08019, Spain
关键词
ITER; shutdown dose rate; direct-one step method; EQUATORIAL PORTS; CROSS-TALK; DIAGNOSTICS;
D O I
10.1088/1741-4326/aac1c5
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 planned in situ maintenance tasks in the ITER port interspace are fundamental to ensure the operation of equipment to control, evaluate and optimize the plasma performance during the entire facility lifetime. They are subject to a limit of shutdown dose rates (SDDR) of 100 mu Sv h(-1) after 10(6) s of cooling time, which is nowadays a design driver for the port plugs as well as the application of ALARA. Three conceptual shielding proposals outside the ITER ports are studied in this work to support the achievement of this objective. Considered one by one, they offer reductions ranging from 25% to 50%, which are rather significant. This paper shows that, by combining these shields, the SDDR as low as 57(Delta) mu Sv h(-1) can be achieved with a local approach considering only radiation from one port (no cross-talk form neighboring ports). The locally evaluated SDDR are well below the limit which is an essential pre-requisite for achieving 100 mu Sv h(-1) in a global analysis including all contributions. Further studies will have to deal with a realistic port plug design and the cross-talks from neighbour ports.
引用
收藏
页数:8
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