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Pitcher, C. S.*; Barnsley, R.*; Bertalot, L.*; Encheva, A.*; Feder, R.*; Friconneau, J. P.*; Hu, Q.*; Levesy, B.*; Loesser, G. D.*; Lyublin, B.*; et al.
Fusion Science and Technology, 64(2), p.118 - 125, 2013/08
被引用回数：4 パーセンタイル：32.48(Nuclear Science & Technology)ITERにおいて計測装置を設置するための基盤構造である上部及び水平ポートプラグの共通部分に関する統合設計をまとめたものである。本設計は、ITER機構が組織した各国数名からなる設計タスクフォースにより実施され、ポートプラグの成立に必要なすべての作業を網羅したものである。検討の結果、一つのポートプラグに複数の計測装置が入る水平ポートプラグでは、計測器毎の干渉を避けると同時に保守を考慮した3から6のユニット構造を提案し、さらに発生する電磁力の低減をはかった。また、真空容器外のインタースペースやポートセルへの設置についても考慮し、ポートプラグ及び計測装置の一体化の検討を行った。会議では懸案となっている中性子遮蔽性能の改善策についても併せて報告する。
Pitcher, C. S.*; Barnsley, R.*; Feder, R.*; Hu, Q.*; Loesser, G. D.*; Lyublin, B.*; Padasalagi, S.*; Pak, S.*; Reichle, R.*; 佐藤 和義; et al.
Fusion Engineering and Design, 87(5-6), p.667 - 674, 2012/08
被引用回数：12 パーセンタイル：66.54(Nuclear Science & Technology)The nuclear engineering infrastructure for port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling.
Pitcher, C. S.*; Andrew, P.*; Barnsley, R.*; Bertalot, L.*; Counsell, G. G.*; Encheva, A.*; Feder, R. E.*; 波多江 仰紀; Johnson, D. W.*; Kim, J.*; et al.
Journal of Nuclear Materials, 415(Suppl.1), p.S1127 - S1132, 2011/08
被引用回数：0 パーセンタイル：0.01(Materials Science, Multidisciplinary)ITER plasma boundary and first-wall diagnostics are summarized in terms of their physical implementation and physics motivation. The challenge of extracting diagnostic signals while maintaining nuclear shielding is discussed, as well as the problems associated with high levels of erosion and redeposition.
Labit, B.*; Pochelon, A.*; Rancic, M.*; Piras, F.*; Bencze, A.*; Bottino, A.*; Brunner, S.*; Camenen, Y.*; Chattopadhyay, P. K.*; Coda, S.*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03
We present recent results on turbulence measurements in TCV L-mode plasmas. The transport reduction at negative triangularity (compared to positive triangularity) is reflected in the reduction of the temperature fluctuation level, in the low frequency part of the spectrum (30-150 kHz), measured by correlation ECE in the outer equatorial plane. The TEM induced transport computed from nonlinear gyrokinetic simulations is shown to decrease with decreasing triangularity and increasing collisionality. First results of an experimental scenario to reach the H-mode regime at negative triangularity in TCV are presented. Then, we report on an innovative divertor magnetic configuration: the snowflake (SF) divertor as opposed to the classical single-null (SN) divertor. For ELMy SF plasmas, the strike-point properties (density, temperature, fluctuation level,...) are studied with Langmuir probes (LPs) and compared with those of a SN configuration obtained within the same discharge.
Walsh, M.*; Andrew, P.*; Barnsley, R.*; Bertalot, L.*; Boivin, R.*; Bora, D.*; Bouhamou, R.*; Ciattaglia, S.*; Costley, A. E.*; Counsell, G.*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2011/03
The ITER device is currently under construction. To fulfil its mission, it will need a set of measurement systems. These systems will have to be robust and satisfy many requirements hitherto unexplored in Tokamaks. Typically, diagnostics occupy either a removable item called a port plug, or installed inside the machine as an intricate part of the overall construction. Limited space availability has meant that many systems have to be grouped together. Installation of the diagnostic systems has to be closely planned with the overall schedule. This paper will describe some of the challenges and systems that are currently being progressed.
