ITER diagnostic port plug engineering design analysis in the EU
Creators
- 1. European Fusion Development Agreement (EFDA), Close Support Unit (CSU), Garching, Boltzmannstr. 2, D-85748 Garching bei Muenchen (Germany)
- 2. ITER International Team, Cadarache (France)
- 3. CEA, Association Euratom-CEA, Commissariat a l'energie Atomique, Cadarache (France)
- 4. UKAEA/EURATOM Fusion Association, Culham Science Centre, Culham (United Kingdom)
- 5. ENEA, Associazione EURATOM-ENEA sulla Fusione, ENEA Centro Ricerche, Frascati (Italy)
- 6. FZK, Forschungszentrum Karlsruhe, Association FZK-EURATOM, Karlsruhe (Germany)
Description
Engineering analysis has been carried out on a representative equatorial diagnostic port plug of ITER, outcome of which is given here. A preliminary overview of the work for a prototypical diagnostic upper port plug is also reported. To ensure that the port plug structure satisfies the requirements of the ITER environment, the following analyses have been performed: finite element (FE) analyses of static and dynamic behaviour under electromagnetic loads, FE vibration analysis, FE thermal-structural analysis and nuclear heating and radiation dose studies. The main outcomes from these analyses and consequent design developments are a revision of the stainless steel/water ratio in the plug neutron shielding modules and the incorporation of improved neutron shielding of the port duct, a modification of the port plug top plate arrangement, to increase torsional stiffness of the structure under disruption loads, and improved solutions for cooling arrangements. Manufacturing studies have also been performed, involving the assessment of methods for the production of plug flanges, the analysis of welding techniques for parts assembly and methods for the introduction of cooling features in plug components. Reference design solutions and possible modifications will be presented and discussed
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2007.08.018Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2007.08.018;
- PII
- S0920-3796(07)00418-8;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 82
- Journal Issue
- 5-14
- Journal Page Range
- p. 1231-1237
- 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
- 39109804
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; DESIGN; ENGINEERING; FINITE ELEMENT METHOD; FLEXIBILITY; ITER TOKAMAK; MODIFICATIONS; NEUTRONS; RADIATION DOSES; SHIELDING; STAINLESS STEELS; WATER; WELDING
- Descriptors DEC
- ALLOYS; BARYONS; CALCULATION METHODS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; DOSES; ELEMENTARY PARTICLES; FABRICATION; FERMIONS; HADRONS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUCLEONS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; STEELS; TENSILE PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.