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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
H.Y. Khater, M.E. Sawan, S..W. Lomperski, I.N. Sviatoslavsky
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 900-905
ITER Nuclear Design | doi.org/10.13182/FST89-A39808
Articles are hosted by Taylor and Francis Online.
Activation analysis was performed for the outboard (o/b) and inboard (i/b) blanket and shield of ITER. The options of using PCA or Tenelon were assessed. The o/b blanket and shield qualify as class C LLW. If Tenelon is used, it qualifies as class A waste. The i/b shield by itself qualifies as class C waste only if Tenelon is used. If PCA is used, then class C qualification can be realized if the i/b and o/b shields are disposed of together. The total amount of 14C produced in the coolant is 4650 Ci for LiNO3 and 54 Ci for LiOH. The Be/SS/W i/b shield results in a decay heat much less than that in an all W shield. Under adiabatic heat-up conditions, the PCA structure can withstand a L0CA and after one day the temperatures do no exceed 700°C.