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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.
Zs. Németh, Á. Veres, I. Pavlicsek, L. Lakosi
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 233-243
Technical Paper | doi.org/10.13182/NSE90-A19188
Articles are hosted by Taylor and Francis Online.
New nondestructive methods for determining burnup and fissile content are introduced. Indium-115 is activated to metastable state by hard gamma rays of a spent-fuel assembly, where the isomer activity produced is proportional to the fissile content. The application of a beryllium converter increases sensitivity by nearly two orders of magnitude and also reduces the time needed. Alternative or simultaneous detection of neutrons emitted by the spent fuel is also available: The produced 116mIn activity is a function of burnup. Principles are verified by many experiments on WWR-SM assemblies. Axial and azimuthal gamma-ray and neutron profiles are also recorded to demonstrate the ability of the methods to detect burnup inhomogeneities. The advantages of the methods and the choice of target material are discussed. Applications for safeguards purposes are suggested.