The design of the high heat flux components of the ITER neutral beam injection system

Authors
Di Pietro, E Inoue, T Krylov, A Murasaka, E Hemsworth, R Alexandrov, E Barinov, M Dlougach, E Kulygin, V Naumov, V Panasenkov, A Petrov, V Fujiwara, Y Ohara, Y Okumura, Y Tanii, M
Citation
E. Di Pietro et al., The design of the high heat flux components of the ITER neutral beam injection system, PLASMA D OP, 6(1-3), 1998, pp. 119-127
Citations number
11
Categorie Soggetti
Nuclear Emgineering
Journal title
PLASMA DEVICES AND OPERATIONS
ISSN journal
10519998 → ACNP
Volume
6
Issue
1-3
Year of publication
1998
Pages
119 - 127
Database
ISI
SICI code
1051-9998(1998)6:1-3<119:TDOTHH>2.0.ZU;2-Z
Abstract
The ITER neutral beam injection system is designed to deliver a total of 50 MW additional heating power to plasma. The system consists of three units, each delivering 16.7 MW. The power balance of each injector shows that to obtain a useful plasma heating of 16.7 MW an electrical input power of appr oximately 50 MW is used, the balance being deposited on the various compone nts of the beam source and beam line. The paper describes the design soluti on utilized for the high heat flux components and discusses the most releva nt aspects of the thermo-mechanical and thermo-hydraulic design.