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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda, Takuya Umano
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 11-33
Technical Paper | doi.org/10.13182/NSE85-A17126
Articles are hosted by Taylor and Francis Online.
The prediction accuracy of the burnup characteristics of large liquid-metal fast breeder reactors (LMFBRs) is very hard to evaluate because of the unavailability of the direct experimental information. A quantitative evaluation was performed on the accuracy of the burnup property by use of the sensitivity coefficients in a large LMFBR and the covariance matrix of nuclear data. Also evaluated was the decrease in prediction error when the cross-section set was adjusted by the use of experimental data, such as criticality, reaction rate ratios, and others. It was concluded that accuracy with the direct use of current nuclear data is ±30% for burnup reactivity loss and ±5% for breeding ratio. On the other hand, the accuracy would be improved to ±18% and ±2.5% by utilizing the experimental data obtained on the zero-power plutonium reactor assembly.