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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.
M. S. Raykin, A. I. Shlyakhter
Nuclear Science and Engineering | Volume 102 | Number 1 | May 1989 | Pages 54-63
Technical Paper | doi.org/10.13182/NSE89-A23631
Articles are hosted by Taylor and Francis Online.
A new approach to the solution of burnup equations is developed that takes into account the dependence of the reaction constants on time as well as nonlinear and feedback effects. With the help of the transition probabilities for the simplified problem, the burnup differential equation is reduced to the equivalent integral equation, which is solved by iterations. The solution is made easy to understand with the help of diagrams constructed following the suggested rules. It is strictly proved that any nuclide transmutation network can be broken into independent depletion chains if the burnup equations are linear in concentrations. The theory is illustrated by examples of the time dependence of reaction constants.