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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.
Nobuhiro Yamamuro
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 128-141
Technical Paper | doi.org/10.13182/NSE91-A28512
Articles are hosted by Taylor and Francis Online.
A model calculation of neutron activation cross sections is carried out with SINCROS-II for all stable isotopes of molybdenum. Results of the calculation are compared with experimental data, which were measured over the wide range from threshold to 20 MeV. The general agreement between the calculated and experimental cross sections is good, but some cross sections remain in significant disagreement. The calculational method is applicable to the estimation of production cross sections for the long-lived radioactive nuclides.
