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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
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.
Ernesto C. Vanterpool, Rudolf E. Slovacek, Donald R. Harris, Robert C. Block
Nuclear Science and Engineering | Volume 110 | Number 2 | February 1992 | Pages 186-194
Technical Notes | doi.org/10.13182/NSE92-A23888
Articles are hosted by Taylor and Francis Online.
Interrogation neutrons from 3 eV to 3 keV are used to determine the relative sensitivity of a spent light water reactor fuel assembly assay system. The fuel assay system used for this measurement consists of three threshold fission chambers installed in the Rensselaer intense neutron spectrometer, a 75-t lead slowing-down-time spectrometer at the Gaerttner Linac Laboratory. The fission chambers detect fission neutrons from a simulated fuel assembly, an aluminum enclosure filled with depleted uranium oxide (0.2% 235U), and a 235U (93%) metal foil sample placed at various locations throughout the assembly. The measurements with the assembly are compared with a Monte Carlo analysis of an homogenized pressurized water reactor fuel assembly. This is concluded to be a practical method for the assay of spent fuel.
