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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.
C. Ronchi, J. Sakellaridis, C. Syros
Nuclear Science and Engineering | Volume 95 | Number 4 | April 1987 | Pages 282-295
Technical Paper | doi.org/10.13182/NSE87-A20439
Articles are hosted by Taylor and Francis Online.
The diffusion equation for volatile radioactive fission products in sintered nuclear fuels is investigated. All known effects that may affect the rate of diffusion to the grain boundaries are taken into account: simultaneous diffusion of the radioactive precursors, radioactive decay, sink trapping, and radiation resolution. Starting from the analysis of the spatial transport equation, an expression for the boundary loss term to be used in the simpler reaction rate equation is deduced. For practical applications the boundary loss term in the absence of resolution effects can reasonably be assumed to be independent of time. This is not generally true if resolution effects are present; in this case the release calculations become more complex than it was assumed so far. Finally, a discussion on the properties of the boundary loss term as functions of the physical parameters involved follows, and details of the calculations are presented.