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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. Pavlik, G. Winkler, M. Uhl, A. Paulsen, H. Liskien
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 186-202
Technical Note | doi.org/10.13182/NSE85-A17676
Articles are hosted by Taylor and Francis Online.
Using activation techniques, the excitation functions for the 58Ni(n,2n)57Ni and 58Ni(n,np + pn + d)57Co reactions were measured in the neutron energy range from 12.7 MeV, close to the (n,2n) threshold, to 19.6 MeV with an accuracy of typically ∼4.5 and ∼6%, respectively. In the 13.4- to 14.8-MeV energy range, the accuracy achieved for the cross sections of the above reactions was typically 2 and 3%, respectively. In addition, cross sections were measured for the 58Ni(n,p)58Co reaction in the 14-MeV region with an accuracy of typically ∼2%. The experimental results were compared with calculations based on the optical model, the compound nucleus model, and the exciton model of nuclear reactions. A quite satisfactory simultaneous reproduction of all experimental data, including the proton- and alpha-production spectrum, was achieved employing a unique set of model parameters. Moreover, the new (n,2n) cross sections provide an improved data base for reactor dosimetry and spectrum unfolding applications.