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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.
A. Hébert, G. Mathonnière
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 129-141
Technical Paper | doi.org/10.13182/NSE115-129
Articles are hosted by Taylor and Francis Online.
Proposals are made for improving current second-generation superhomogénéisation (SPH) methods in three different ways and to use them in heterogeneous and homogeneous diffusion procedures for reactor design and operating calculations. The first improvement consists of using a surface radial leakage model in the flux calculation to represent the macroscopic flux curvature in the assembly. The second improvement is accomplished by the introduction of the Selengut normalization in the SPH equivalence procedure replacing the flux-volume normalization currently used with second-generation methods. Finally, the buckling calculation is improved to better represent the target color-set. Second- and third-generation SPH techniques for heterogeneous or homogeneous diffusion procedures are now implemented as a unified algorithm in a lattice code. Two-group benchmarks are proposed to measure precisely the equivalence effectiveness and the improvement gained with third-generation methods.