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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.
Yuan Chen, Gang Chen, Rong Liu, Haiping Guo, Wenjiang Chen, Wenmian Jiang, Jian Shen
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1919-1924
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29622
Articles are hosted by Taylor and Francis Online.
Using the Total Absorption Method, the neutron multiplications in beryllium have been measured. A deionized water sphere with outer radius of 75 cm and a polyethylene sphere with outer radius of 69 cm were used as the total neutron absorbers. Neutron distributions in the spheres were measured using 235U fission chambers. The relative and the efficiency-determined methods were compared. Important sources of experimental errors were detailly analyzed. 4 groups of neutron multiplications in beryllium up to 14.85 cm thick for two total absorbers and two methods of measurement have been obtained and agreement among them is satisfactory. Measured results have been compared with ANISN calculations using data from ENDF/B-IV. It is shown that the differences between calculations and experiments are up to 15%.
