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May 31–June 3, 2026
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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.
Toshikazu Takeda, Hironobu Unesaki, Tamotsu Sekiya, Keisho Shirakata
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 538-548
Technical Paper | doi.org/10.13182/NSE88-A23586
Articles are hosted by Taylor and Francis Online.
To solve the problems encountered in the analysis of the large homogeneous and heterogeneous fast critical assemblies, Zero-Power Plutonium Reactor (ZPPR) 9, 10, and 13, we have revisited the analysis using improved methods. Two-dimensional cell calculations, cell calculations using multidrawer cell models, and three-dimensional transport theory core calculations were introduced. Using these methods, the discrepancies in the calculation-to-experiment (C/E) values of keff for the fast critical assemblies was reduced. The use of the multidrawer model reduced the C/E spatial dependency of the control rod worths in the ZPPR-10 cores. To investigate the remaining problems of the spatial dependence of the C/E values of reaction rate distribution and control rod worth, we have adjusted a cross-section set obtained from the JENDL-2 library using the integral experiments. The cross-section changes, particularly for the diffusion coefficient, 238U scattering and capture, and 239Pu fission cross sections, have corrected the spatial dependence, as well as the overestimation of the 238U capture to 239Pu fission rate ratio and sodium void worth.