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May 31–June 3, 2026
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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.
George Patrick Lasche
Nuclear Science and Engineering | Volume 83 | Number 1 | January 1983 | Pages 162-173
Technical Paper | doi.org/10.13182/NSE83-A17997
Articles are hosted by Taylor and Francis Online.
A “back-of-the-envelope” method is presented for estimating neutron-induced radionuclide populations. The method uses energy-averaged neutron-reaction cross sections as base data and accounts for nonequilibrium nuclide formation by any sequence of transmutations; it provides for cases in which nuclides in transmutation sequences may be produced in more than one way or may decay or react to produce more than one product nuclide, and it accounts for both constant physical removal from circulating fluids and the severe depletion of parent nuclei. Evaluation in a series of time steps is not required; the calculation is done only for the time of interest. Estimates of neutron-induced radionuclide populations are made from the sum of population contributions corresponding to the most significant transmutation sequences by which the radionuclide is formed. Transmutation sequences are defined in such a way that population contributions corresponding to them can be evaluated from either exact analytic solutions or from a simple approximate procedure that always yields an upper bound to population contribution.