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.2007.03.019Additional 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.