TY - JOUR
T1 - Study of Radioactive Inventory Generated from W-based Components in ITER and PPCS Fusion Designs
AU - Desecures, Mikaël
AU - El-Guebaly, Laila
AU - Druyts, Frank
AU - Van Iseghem, Pierre
N1 - Score = 10
PY - 2013/10
Y1 - 2013/10
N2 - 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. We 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, we examined the three radioactive waste management options (disposal, recycling, and clearance) as well as the transmutation of W. 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 divertor W is <1%. Such a low transmutation level may not impair the physical properties of divertor W alloys.
AB - 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. We 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, we examined the three radioactive waste management options (disposal, recycling, and clearance) as well as the transmutation of W. 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 divertor W is <1%. Such a low transmutation level may not impair the physical properties of divertor W alloys.
KW - tungsten-based divertor
KW - tungsten recycling
KW - tungsten transmutation
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_134510
UR - http://knowledgecentre.sckcen.be/so2/bibref/11318
U2 - 10.1016/j.fusengdes.2013.02.042
DO - 10.1016/j.fusengdes.2013.02.042
M3 - Article
SN - 0920-3796
VL - 88
SP - 2674
EP - 2678
JO - fusion engineering and design
JF - fusion engineering and design
IS - 9-10
T2 - Proceedings of the 27th Symposium On Fusion Technology (SOFT-27); Liège, Belgium, September 24-28, 2012
Y2 - 24 September 2012 through 28 September 2012
ER -