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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.
Myung H. Kim, A. F. Henry
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 276-282
Technical Paper | doi.org/10.13182/NSE89-A23678
Articles are hosted by Taylor and Francis Online.
Equations for a few-group model applicable to transient analysis are derived from a variational principle made stationary by the continuous-energy P1, equations. Flux-adjoint (bilin-early) weighted few-group parameters result. These can be reduced to the regular flux-spectrum weighted parameters by taking the adjoint spectrum to be constant in energy. Numerical comparisons with multigroup results show that both regular and bilinearly weighted two-group models provide acceptably accurate predictions of transient behavior when realistic pressurized water reactor cases are examined. Although there are still some theoretical questions to be examined, there appears at present to be no reason to employ bilinearly weighted parameters for either static or transient analysis.