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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.
Vijay R. Nargundkar, Mahadeva Srinivasan, Om Prakash Joneja
Fusion Science and Technology | Volume 13 | Number 1 | January 1988 | Pages 153-156
Technical Paper | Blanket Engineering | doi.org/10.13182/FST88-A25092
Articles are hosted by Taylor and Francis Online.
Four basic configurations, block, homogeneous, multilayered, and heterogeneous systems, for tritium breeding in natural lithium water-reflected fusion blankets are compared. A 14-MeV point neutron source is used with a lead multiplier. All the calculations are done in rectangular geometry with the Monte Carlo code MORSE-E and Los Alamos National Laboratory's 30-group neutron cross-section set CLAW-IV in P3 scattering approximation. The homogeneous system gives the best and the block concept gives the lowest tritium breeding, but neither of these concepts is practical for use infusion blankets. Among the practical blanket arrangements, for equal amounts of natural lithium and water, the heterogeneous and multilayered arrangements give almost identical tritium breeding.