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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.
K. Raschke, T. Straume
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 282-286
Technical Note | doi.org/10.13182/NSE86-A17273
Articles are hosted by Taylor and Francis Online.
As part of the Nevada Nuclear Waste Storage Investigations, the Lawrence Livermore National Laboratory conducted a test for the U.S. Department of Energy to evaluate both the feasibility of deep geologic storage and the safety of handling spent nuclear fuel assemblies. The radiological monitoring and dosimetry program instituted for the Spent Fuel Test-Climax is discussed. During the 3-yr storage phase of the test, no measurable radioactive effluent was released. Radiation exposures to personnel handling the shielded spent fuel assemblies (∼500 Gy/h at contact when unshielded) were <4 person-mSv for the duration of the project. The dosimetry data extrapolated to proposed large-scale storage schemes indicate that personnel exposures would be within currently accepted annual guidelines. The dose commitment in person-sieverts resulting from spent fuel emplacement and storage is extrapolated to be ∼0.2% of that currently received in the normal operation of nuclear power plants.