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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.
D. W. Wootan, J. A. Rawlins, L. L. Carter, H. R. Brager, R. E. Schenter
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 150-156
Technical Paper | doi.org/10.13182/NSE89-A28503
Articles are hosted by Taylor and Francis Online.
A cobalt test assembly containing yttrium hydride pins for neutron moderation was irradiated in the Fast Flux Test Facility (FFTF) during cycle 9A for 137.7 equivalent full-power days at a power level of 291 MW. The 36 test pins consisted of a batch of 32 pins containing cobalt metal used to produce 60Co and a set of four pins with europium oxide to produce 153Gd, a radioisotope used in detection of the bone disease osteoporosis. Postirradiation examination of the cobalt pins determined the 60Co production to be predictable to an accuracy of ∼5 %. The measured 60Co spatially distributed concentrations were within 20% of the calculated concentrations. The assembly average 60Co measured activity was 4% less than the calculated value. The europium oxide pins were gamma scanned for the europium isotopes 152Eu and 154Eu to an absolute accuracy of -10%. The measured europium radioisotope and I53Gd concentrations were within 20% of calculated values. The hydride assembly performed well and is an excellent vehicle for many FFTF isotope production applications. The results also demonstrate the accuracy of the calculational methods developed by the Westinghouse Hanford Company for predicting isotope production rates in this type of assembly.