Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code

Youssef, M.Z.; Feder, R.

doi:10.1016/j.fusengdes.2012.02.079

Cited by 7 publications

(3 citation statements)

References 7 publications

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“…In contrast to the full ITER 20-degree B-Lite model used in previous studies [4][5], a simplified 20-degree ITER model is used in the present calculations and is shown in Fig. 2.…”

Section: B Calculation Model and Assumptions Appliedmentioning

confidence: 99%

Assessment and optimization of the interspace dose rate of the diagnostics equatorial port plug #3 in ITER with Attila

Youssef¹,

Feder²

2013

2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

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According to ITER integration procurement arrangements, the installment of diagnostics in a port should not increase the shutdown dose rate (SDDR) in the port interspace area by no more than ~50 microSv/hr above the baseline, assuming another 50 microSv/hr is attributed to contribution from the port structure and other ITER in-vessel components, such that the upper SDDR limit of 100 microSv/hr is not exceeded 10 6 s after shutdown. It was found that placing the initial design of the Motional Stark Effect, MSE, and the Charge Exchange Recombination Spectroscopy, CXRS, in the equatorial port #3 (EPP3) resulted in an increase in the SDDR that far exceeded the limit. When we follow the optimization process discussed in this paper, substantial reduction in the port interspace SDDR was achieved. The results of the present work show that even when we combine the optimized CXRS and MSE diagnostics with a third GDC diagnostic, the excess of the SDDR over the baseline value did not exceed the allowed upper limit. The present work is based on utilizing the 3-D CAD-based Attila code for assessing the SDDR.

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“…In contrast to the full ITER 20-degree B-Lite model used in previous studies [4][5], a simplified 20-degree ITER model is used in the present calculations and is shown in Fig. 2.…”

Section: B Calculation Model and Assumptions Appliedmentioning

confidence: 99%

Assessment and optimization of the interspace dose rate of the diagnostics equatorial port plug #3 in ITER with Attila

Youssef¹,

Feder²

2013

2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

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show abstract

“…The situation in the ITER EPs is particularly challenging, due to their proximity to the plasma, the port plug weight restrictions, the limited space for shielding and the relative orientation with respect to the plasma. A collection of works showing current status is [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

“…Large efforts to reduce the SDDR in the ITER port interspaces have been devoted to improve the design of the port plugs as understood from works [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15][16]. In example, for Diagnostics port plugs, works to develop a long diagnostics shield module (DSM) for a satisfactory port plug integration are in progress [17].…”

Section: Introductionmentioning

confidence: 99%

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

et al. 2018

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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 µSv h−1 after 106 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 57Δ µSv 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 100µSv 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.

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Benchmarking of the 3-D CAD-based Discrete Ordinates code “ATTILA” for dose rate calculations against experiments and Monte Carlo calculations

Youssef

Feder

Batistoni

et al. 2013

Fusion Engineering and Design

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Global dose rate assessment in ITER diagnostics ports based on the 3-D FEM ATTILA code

Cited by 7 publications

References 7 publications

Assessment and optimization of the interspace dose rate of the diagnostics equatorial port plug #3 in ITER with Attila

Assessment and optimization of the interspace dose rate of the diagnostics equatorial port plug #3 in ITER with Attila

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

Benchmarking of the 3-D CAD-based Discrete Ordinates code “ATTILA” for dose rate calculations against experiments and Monte Carlo calculations

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