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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.
Abderrafi M. Ougouag , Hrabri L. Rajic
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 332-341
Technical Paper | doi.org/10.13182/NSE100-332
Articles are hosted by Taylor and Francis Online.
A self-consistent nodal method has been developed that directly computes the in-node flux shapes. The method renders the use of an approximation for the transverse leakages no longer necessary. These are obtained directly from the available interface net current shapes, interface flux shapes, and in-node fluxes. The order of the transverse leakage expansion on a set of Legendre polynomials is determined by the order chosen for the method. The results yielded are nearly as accurate (0.02% maximum relative assembly power error) as very fine-mesh benchmark solutions. A comprehensive numerical and analytical analysis of the transverse leakage approximation has been performed. It has been shown that the quadratic leakage approximation can be in error by many times its value. The success of the quadratic leakage approximation is attributed to its small effect on the nodal powers. The theory developed shows that the transverse leakages can have shapes that encompass hyperbolic sines and cosines, and hence that their approximation via quadratic expansions should not always be expected to be adequate. The ILLICO-HO method gives much more information (detailed fluxes and interface currents) than comparable finite difference as well as nodal benchmark solution methods.