Technologies for the ITER divertor vertical target plasma facing components
Creators
- 1. Ass. Euratom-CEA, DSM/DRFC, CEA/Cadarache, St Paul Lez Durance (France)
- 2. EFDA Garching (Germany)
- 3. ITER Team, Garching (Germany)
- 4. Forschungszentrum, Juelich (Germany)
Description
The ITER divertor vertical target (VT) has to sustain heat fluxes up to 20 MW/m2. The concept developed for this Plasma Facing Component (PFC) working at steady state is based on Carbon Fibre Composite (CFC) armour for the lower straight part and tungsten (W) for the curved upper part. The main challenges of such components are to be able to remove the high deposited heat fluxes and to join mechanically and thermally armour to the metallic heat sink, despite of the mismatch of the thermal expansions. Two solutions based on the use of CuCrZr hardened copper alloy and active metal casting (AMC) process were investigated during the ITER EDA phase: the first one called 'flat tile geometry' was mainly developed for Tore Supra pumped limiter, the second one called 'monoblock geometry' was developed by the EU Participating Team for the ITER project. This paper presents a review of these two solutions and analyses their assets and drawbacks: pressure drop, critical heat flux, surface temperature and expected behaviour during operation, risks during the manufacture, controls of the armour defects during the manufacture and at the reception and possibility to repair defected tiles. (author)
Files
36080636.pdf
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Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-100405-2
- Imprint Title
- 20th IAEA fusion energy conference 2004. Conference proceedings
- Imprint Pagination
- 3451 p.
- Journal Issue
- no. 25/CD
- Series
- C and S papers series
- Journal Page Range
- [8 p.]
- ISSN
- 1562-4153
- Report number
- IAEA-CSP--25/CD
Conference
- Title
- 20. IAEA fusion energy conference 2004
- Dates
- 1-6 Nov 2004
- Place
- Villamoura (Portugal)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36080636
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON FIBERS; CONTROL; COPPER ALLOYS; CRITICAL HEAT FLUX; DIVERTORS; FIRST WALL; GEOMETRY; HEAT SINKS; ITER TOKAMAK; OPERATION; PRESSURE DROP; PUMPED LIMITERS; THERMAL EXPANSION; THERMONUCLEAR REACTOR MATERIALS; TORE SUPRA TOKAMAK; TUNGSTEN
- Descriptors DEC
- ALLOYS; CLOSED PLASMA DEVICES; ELEMENTS; EXPANSION; FIBERS; HEAT FLUX; LIMITERS; MATERIALS; MATHEMATICS; METALS; REFRACTORY METALS; SINKS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS
Optional Information
- Notes
- 20 refs, 7 figs, 4 tabs
- Secondary number(s)
- FT/P1--23