Published December 1999 | Version v1
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ITER in-vessel system design and performance

Creators

  • 1. ITER Garching Joint Work Site, Max-Planck-Institut fuer Plasmaphysik, Garching (Germany)

Description

This paper reviews the design and performance of the in-vessel components of ITER as developed for the EDA Final Design Report (FDR). The double-wall vessel is the first confinement boundary and is designed to maintain its integrity under all normal and off-normal conditions, e.g., the most intense VDE's and seismic events. The shielding blanket consists of modules connected to a toroidal backplate by flexible connectors which allow differential displacements due to temperature differences. Breeding blanket modules replace the shield modules for the Enhanced Performance Phase. The divertor is based on a cassette structure which is convenient for remote installation and removal. High heat flux (HHF) components are mechanically attached and can be removed and replaced in the hot cell. Operation of the divertor is based on achieving partially detached plasma conditions along and near the separatrix. Nominal heat loads of 5-10 MW/m2 are expected and these are accommodated by HHF technology developed during the EDA. Disruptions and VDE's can lead to melting of the first wall armour but no damage to the underlying structure. Stresses in the main structural components remain within allowables for all postulated disruption and seismic events. (author)

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Part of:
Fusion energy 1998. Proceedings. V. 1-4

Additional details

Publishing Information

Imprint Title
Fusion energy 1998. Proceedings. V. 1-4
Imprint Pagination
1721 p.
Journal Issue
no. 1/P
Series
C and S papers series
Journal Page Range
v. 3 p. 939-946
ISSN
1563-0153
Report number
IAEA-CSP--1/P

Conference

Title
17. IAEA fusion energy conference
Dates
18-24 Oct 1998
Place
Yokohama (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31011405
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; DIVERTORS; FIRST WALL; ITER TOKAMAK; LINERS; MEETINGS; PLASMA DIAGNOSTICS
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
22 refs, 5 figs
Secondary number(s)
ITER--2