European programme towards the 1 MeV ITER NB injector

被引:27
作者
Masiello, A. [1 ]
Agarici, G. [1 ]
Bonicelli, T. [1 ]
Simon, M. [1 ]
Antoni, V. [2 ]
De Esch, H. [3 ]
De Lorenzi, A. [2 ]
Dremel, M. [4 ]
Franzen, P. [5 ]
Hemsworth, R. [6 ]
Liniers, M. [7 ]
Marcuzzi, D. [2 ]
Martin, D. [8 ]
Piovan, R. [2 ]
Simonin, A. [3 ]
Sonato, P. [2 ]
Surrey, E.
Svensson, L. [3 ]
Tanga, A.
Toigo, V. [2 ]
Waldon, C. [8 ]
Zaccaria, P. [2 ]
机构
[1] Fus Energy, Barcelona 08019, Spain
[2] Euratom ENEA Assoc, Consorzio RFX, I-35126 Padua, Italy
[3] IRFM SCCP, CEA Cadarache, EURATOM Assoc, F-13108 St Paul Les Durance, France
[4] EURATOM, Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[5] EURATOM, Max Planck Inst Plasmaphys, D-85740 Garching, Germany
[6] CEA Cadarache, ITER Joint Work Site, F-13108 St Paul Les Durance, France
[7] Assoc EURATOM CIEMAT, Madrid 28040, Spain
[8] Culham Sci Ctr, UKAEA Fus Assoc, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
Plasma heating; NB system;
D O I
10.1016/j.fusengdes.2008.12.090
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
The ITER neutral beam (NB) system presents several challenges and a robust program is necessary in order to achieve the requirements within the tight constraints due to the ITER construction plan. The establishment of full scale NB test facilities (NBTF) has therefore become a centre piece of the international NB development strategy. This paper describes the status of the design activities that have been undertaken in Europe to develop the components for the heating NB injectors along with the main plans and results of the R&D activities. A description of the programme towards the establishment of the test facilities and the planned activities is also reported. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:1276 / 1280
页数:5
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