Nuclear engineering of diagnostic port plugs on ITER
Creators
- 1. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)
- 2. Princeton Plasma Physics Lab, Princeton, NJ (United States)
- 3. Institute of Plasma Physics, Chinese Academy of Sciences (China)
- 4. Efremov, St. Petersburg (Russian Federation)
- 5. Institute for Plasma Research, Gandhinagar, Gujarat (India)
- 6. National Fusion Research Institute, Daejeon (Korea, Republic of)
- 7. Japan Atomic Energy Agency, Naka, Ibaraki (Japan)
Description
The nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling. A modular approach is adopted for the internal shielding modules as this helps to reduce the dominant electromagnetic loads, reduces interfaces and accelerates remote handling. Extensive use of gun-drilling is employed to produce water channels in the stainless steel plate and forgings used to construct the port plugs and modules. The French Nuclear Code RCC-MR (2007) is employed in the design and the manufacturing. An integrated remote handling scheme is described, including a description of maintenance operations in the Hot Cell Facility.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2012.01.043Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2012.01.043;
- PII
- S0920-3796(12)00054-3;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 87
- Journal Issue
- 5-6
- Journal Page Range
- p. 667-674
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 10. international symposium on fusion nuclear technology
- Acronym
- ISFNT-10
- Dates
- 11-16 Sep 2011
- Place
- Portland, OR (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44037055
- Subject category
- S42: ENGINEERING; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLOSURES; DESIGN; DRILLING; FORGING; HOT CELLS; ITER TOKAMAK; MANUFACTURING; NUCLEAR ENGINEERING; PLATES; REMOTE HANDLING; SHIELDING; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; ENGINEERING; EQUIPMENT; FABRICATION; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LABORATORY EQUIPMENT; MATERIALS WORKING; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.