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INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
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.