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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.
Koji Oishi, Yujiro Ikeda, Hiroshi Maekawa, Tomoo Nakamura
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 46-58
Technical Paper | doi.org/10.13182/NSE89-A23659
Articles are hosted by Taylor and Francis Online.
The neutron spectra in a concrete assembly bombarded by 14-MeV neutrons are measured by a miniature NE-213 spectrometer and the multifoil activation method. The results obtained are within experimental error. The measured spectra are compared with calculated results obtained using the two-dimensional DOT3.5 transport code with 125-group structure cross-section libraries based on ENDF/B—IV, JENDL-2, and JENDL-3T (the test version of JENDL-3). In the deuterium-tritium neutron peak region, the measured and calculated neutron spectra are in agreement. However, all the calculations overestimate the measurements by 10 to 50% in the mega-electron-volt region. In a still lower neutron energy range, where the 197Au(n,γ)198Au reaction is dominant, discrepancies from −30 to +40% are observed. Possible reasons are considered, but none explain the discrepancies. Further investigation of the secondary neutrons in the mega-electron-volt region emitted by elastic and inelastic scattering from the main components of concrete, such as oxygen, silicon, and calcium, is necessary to improve the agreement between experimental and calculated results.