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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.
Norman E. Holden, Martin S. Zucker
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 174-181
Technical Paper | doi.org/10.13182/NSE88-A28498
Articles are hosted by Taylor and Francis Online.
The prompt neutron emission multiplicity distribution Pv and its average value 〈v〉 (i.e., nubar) have been determined at the standard neutron energy of 0.0253 eV for the neutron-induced fission of the four fissile nuclides 233,235 U and 239,241Pu. Revised values of 〈v〉 have been obtained by reevaluating 〈v〉 experiments measured at 2200 m/s relative to the 〈v〉 from the spontaneous fission of 252Cf. These revised values of 〈v〉 have been used to renormalize the measured Pv values. The revised values of (v) are all ∼0.25 to 0.5% smaller than the corresponding values of ENDF/B-V.