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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.
L.J. Perkins, G.L. Kulcinski
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1107-1112
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23006
Articles are hosted by Taylor and Francis Online.
A self-consistent procedure has been established for economic design optimization of the lithium-lead (LiPb) blanket for the MARS tandem mirror reactor. The procedure is necessarily iterative and enables progress in blanket design to be assessed in terms of the minimization of an economic figure of merit F for the complete reactor system. Typical economic design questions regarding blanket and central cell parameters such as tritium breeding ratio, neutron energy multiplication factor, thermal cycle efficiency, blanket radial thickness, magnet radii, etc., can then be addressed in terms of their influence on overall system costs. This procedure is not necessarily specific to MARS and has general applicability to fusion reactor blanket design optimization. Application of the procedure resulted in a blanket with small (∼ 38 cm) radial thickness, highly enriched (90%) lithium, adequate tritium breeding ratio (1.14) and a neutron energy multiplication and thermal efficiency approaching those for blankets of considerably larger radial dimensions.