Study of radioactive inventory generated from W-based components in ITER and PPCS fusion designs
Creators
- 1. Ghent University, Ghent (Belgium)
- 2. University of Wisconsin, Madison, WI (United States)
- 3. Belgian Nuclear Research Center, Mol (Belgium)
Description
Highlights: ► Recycling and clearance would be a potential solution to reduce the radioactive inventory. ► Both ITER and PPCS divertors ultimately classify MA-VL according to French regulations. ► The most attractive alloys appear to be W–1%Ta, W–TiC, W–K and W–La2O3. ► W transmutation strongly depends on the neutron spectrum and fluence. -- Abstract: Tungsten and its alloys are currently considered as prime candidates for plasma facing components in many fusion experimental devices and power plants, but some issues regarding the activation of these materials remain to be clarified. This study has addressed the activation concerns of seven candidate W-alloys (W–W composites, W–La2O3, W–TiC, W–Ta, W–K, VM tungsten and W–Re) that could be used for W-based divertors and W-armors under the operating conditions of the ITER experimental facility and the PPCS power plant (EU power plant design studies). More specifically, the three radioactive waste management options (disposal, recycling, and clearance) as well as the transmutation of W have been examined. The latter is quite sensitive to the divertor and blanket materials. About 5–8 at.% of the W-armor transmute at the end of the PPCS blanket lifetime while the transmutation in the W-based divertor is <1%. Such a low transmutation level may not impair the physical properties of divertor W-alloys
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2013.02.042Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2013.02.042;
- PII
- S0920-3796(13)00157-9;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 88
- Journal Issue
- 9-10
- Journal Page Range
- p. 2674-2678
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 27. symposium on fusion technology
- Acronym
- SOFT-27
- Dates
- 24-28 Sep 2012
- Place
- Liege (Belgium)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45054105
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOYS; DESIGN; DIVERTORS; EQUIPMENT; FIRST WALL; INVENTORIES; ITER TOKAMAK; LIFETIME; NEUTRON SPECTRA; PHYSICAL PROPERTIES; POWER PLANTS; RADIOACTIVE WASTE MANAGEMENT; RECYCLING; TRANSMUTATION; TUNGSTEN
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELEMENTS; MANAGEMENT; METALS; REFRACTORY METALS; SPECTRA; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS; WASTE MANAGEMENT
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.