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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.
A. A. Vankov and V. F. Ukraintsev, N. Yaneva, S. Toshkov, A. Mateeva
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE87-A16372
Articles are hosted by Taylor and Francis Online.
Transmission and fission self-indication were measured for the isotopes 235U, 238U, and 239Pu in the unresolved resonance region for a wide range of material thicknesses. The fission cross section of 235U serves as standard. The other isotopes are the basic fuel components in plutonium fast breeder reactors., The experimental results obtained were analyzed together with average cross-section data using the multilevel R-matrix formalism. The objective of the consistent analysis was to estimate sets of mean resonance parameters. For this purpose, a new multilevel ladder technique was developed (Monte Carlo method) that enabled calculation of all the functionals of interest including their sensitivity coefficients related to the mean resonance parameters. Hence, the perturbation approach and the correlated random sampling technique were employed., The method of evaluation was strictly statistical, allowing a priori information on the parameters to be used. Thus, a new consistent evaluation of the mean resonance parameters under consideration and of the whole table of group constants requested was performed., The results are discussed with respect to their reliability in practical applications.