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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.
M. F. Sulcoski, H. D. Warren
Nuclear Science and Engineering | Volume 85 | Number 3 | November 1983 | Pages 245-250
Technical Paper | doi.org/10.13182/NSE83-A17316
Articles are hosted by Taylor and Francis Online.
The thermal neutron sensitivities of 231Rh self-powered neutron detectors were measured in a 1-MW(thermal) pool-type reactor. Measured relative sensitivities are statistically compared against calculated relative sensitivities. The latter are derived from a formula for the ratio of the lateral surface area of the rhodium emitter of a given detector to the lateral surface area of the rhodium emitter of a reference detector. Least-squares linear regression analysis of relative sensitivity versus surface area shows that the calculational method yields the same calibration results as the measured method with a high degree of accuracy.