Published October 2007 | Version v1
Journal article

High heat flux (HHF) elements for negative ion systems on ITER

  • 1. Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)

Description

Negative Ion Neutral Beam systems on ITER will require actively cooled scrapers and dumps to process and shape the beam before injection into the tokamak. The scale of the systems is much larger than any presently operating, bringing challenges for designers in terms of available sub cooling, total pressure drop, deflection and mandatory remote maintenance. High heat fluxes (∼15-20 MW/m2), pulse lengths in excess of 3000 s and high number of cycles pose new challenges in terms of stress and fatigue life. The designs outlined in the Design Description Document for the ITER Neutral Beam System [N53 DDD 29 01-07-03 R 0.1. ITER Design Description Document, DDD 5.3, Neutral Beam H and CD system (including Appendices).], based on swirl tubes, have been reviewed as part of the design process and recommendations made. Additionally, alternative designs have been proposed based on the Hypervapotron high heat flux elements with modified geometry and drawing upon a vast background knowledge of large scale equipment procurement and integration. A full thermo-mechanical analysis of all HHF components has also been undertaken based on ITER design criteria and the limited material data available. The advantages and disadvantages of all designs are presented and recommendations for improvements discussed

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2007.03.019

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2007.03.019;
PII
S0920-3796(07)00109-3;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
82
Journal Issue
5-14
Journal Page Range
p. 945-952
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
24. symposium on fusion technology
Acronym
SOFT-24
Dates
11-15 Sep 2006
Place
Warsaw (Poland)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39068677
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANIONS; BEAMS; COOLING; DESIGN; DRAWING; FATIGUE; GEOMETRY; HEAT FLUX; ITER TOKAMAK; MAINTENANCE; PRESSURE DROP; PULSES; RECOMMENDATIONS; SCRAPERS; SHAPE; STRESSES; TUBES
Descriptors DEC
CHARGED PARTICLES; CLOSED PLASMA DEVICES; EQUIPMENT; FABRICATION; IONS; MATERIALS WORKING; MATHEMATICS; MECHANICAL PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.