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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.
Jorge Molina Avila, Maria Do Carmo Lopes
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 310-317
Technical Paper | doi.org/10.13182/NSE87-A16394
Articles are hosted by Taylor and Francis Online.
A previously developed formalism is applied to calculate the sensitivity of cobalt prompt response self-powered neutron detectors. Differential and average sensitivities in thermal and epithermal energy regions are calculated, and their dependence on the geometrical factors is studied. A simple analytical expression is proposed for the first-collision absorption probability, which is a good approximation to the exact function. This expression is used to obtain the epithermal selfshielding factor as a function of the radius of the emitter and the parameters of the interaction. The thermal sensitivity, as the main contributor to the current, is studied as a function of the emitter radius. Finally, a criterion to evaluate the accuracy of the parameters of the model is established in the form of some interval rule. This interval rule should encourage the performance of better measurements and calculations.