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.
|Journal||fusion engineering and design|
|State||Published - Oct 2013|
|Event||Proceedings of the 27th Symposium On Fusion Technology (SOFT-27); Liège, Belgium, September 24-28, 2012 - SCK•CEN, Liège|
Duration: 24 Sep 2012 → 28 Sep 2012