Fatigue lifetime of repaired high heat flux components for ITER divertor
Creators
- 1. CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France)
- 2. Fusion For Energy, 08019 Barcelona (Spain)
- 3. AREVA NP PTCMI-F, Centre Technique, Fusion, 71200, Le Creusot (France)
Description
Thermal fatigue behaviour of repaired monoblocks was assessed from High Heat Flux (HHF) tests up to 20 MW m-2 on 11 components. Among these components, 8 monoblocks were repaired (2 CFC and 6 tungsten). These components were manufactured by two EU industries: ANSALDO Ricerche and PLANSEE. Non destructive examination was performed on SATIR thermography test bed before and after HHF tests. SATIR results show that repaired monoblocks have a good thermal exhaust capability before HHF tests. For all monoblocks, no degradation of thermal properties was noticed during cycles at 10 MW m-2. After hundreds of cycles at 20 MW m-2, two W repaired monoblock melted. Post-HHF SATIR examination revealed a degradation of thermal properties which is systematic for W melted monoblocks and non-systematic for W repaired ones. For CFC repaired monoblocks, no damage was observed up to 20 MW m-2. For the first ITER divertor set, specifications for the pre-qualification are that CFC (Resp. W) components have to sustain in steady state 1000 cycles at 10 MW m-2 (Resp. 3 MW m-2) followed by 1000 cycles at 20 MW m-2 (Resp. 5 MW m-2). For the first ITER divertor set, the repair process is validated for CFC and W monoblocks.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2011.03.020Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2011.03.020;
- PII
- S0920-3796(11)00292-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 86
- Journal Issue
- 9-11
- Journal Page Range
- p. 1771-1775
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 26. symposium on fusion technology
- Acronym
- SOFT-26
- Dates
- 27 Sep - 1 Oct 2010
- Place
- Porto (Portugal)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43067950
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON FIBERS; COMPOSITE MATERIALS; DIVERTORS; FIRST WALL; HEAT FLUX; ITER TOKAMAK; THERMAL FATIGUE; THERMODYNAMIC PROPERTIES; THERMOGRAPHY; TUNGSTEN
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELEMENTS; FATIGUE; FIBERS; MATERIALS; MEASURING METHODS; MECHANICAL PROPERTIES; METALS; PHYSICAL PROPERTIES; REFRACTORY METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.