Published November 2005 | Version v1
Journal article

Special blanket design in the NB region of ITER

  • 1. ITER Garching Joint Work Site, Boltzmannstrasse 2, 85748 Garching (Germany)

Description

The paper explains the evolution of the ITER blanket design in the Neutral Beam (NB) region and the compromise among the requirements of many interacting components, such as the blanket with the first wall, the vacuum vessel and its penetrations, the NB system, the coolant manifolds and the toroidal field coils. At first a design constrained by the square shape of the blanket modules is presented, as was adopted in ITER 2001. Then, a new design is described with three special modules around the NB penetration and regular modules elsewhere. The acceptance of more complex design in a few modules improves significantly the configuration of the blanket, the strength of the module attachment and the maintenance of the machine

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2005.06.106;
PII
S0920-3796(05)00234-6;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
75-79
Journal Page Range
p. 601-605
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
23. symposium of fusion technology
Acronym
SOFT 23
Dates
20-24 Sep 2004
Place
Venice (Italy)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37109156
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BEAM INJECTION HEATING; COOLANTS; DESIGN; FIRST WALL; ITER TOKAMAK; MAINTENANCE; NEUTRAL ATOM BEAM INJECTION
Descriptors DEC
BEAM INJECTION; CLOSED PLASMA DEVICES; HEATING; PLASMA HEATING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.