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Latest News
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.
Anil Kumar, Cherif Sahraoui
Fusion Science and Technology | Volume 13 | Number 3 | March 1988 | Pages 484-494
Technical Paper | Alpha-Particle Workshop / Blanket Engineering | doi.org/10.13182/FST88-A25126
Articles are hosted by Taylor and Francis Online.
Reaction rates of 115In(n, n′) and 90Zr(n,2n) were measured on various axial positions inside single slabs of 18-cm-thick beryllium and 15-cm-thick lead kept in front of a Haefely deuterium-tritium neutron generator. These experimental axial activity profiles, and those for the zirconium/indium ratio, are compared to those computed using the two-dimensional discrete ordinates code DOT 3.5 coupled to a compatible first-collision source evaluator code GREATUNCL. Generally, a satisfactory agreement is seen between these profiles for both beryllium and lead slabs.
