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May 31–June 3, 2026
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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.
S. Pelloni, J. Stepanek, D. J. Dudziaka)
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1189-1194
Neutronics and Shielding | doi.org/10.13182/FST83-A23020
Articles are hosted by Taylor and Francis Online.
The European Community International Tokamak Reactor (INTOR-EC) was used to investigate the influence of different cross-section libraries on the tritium breeding ratio. Nucleonic analyses were performed using the discrete-ordinates transport codes ANISN and ONEDANT, and the recently developed Swiss surface-flux code SURCU. Nuclear data considered were from the DLC-37, VITAMIN-C (DLC-41 ), Los Alamos-NJOY and MACKLIB-IV fusion libraries. It is shown that very good agreement (within 0.5%) between the breeding ratios obtained using the VITAMIN-C and Los Alamos libraries could be obtained, whereas the corresponding values calculated using VITAMIN-C and MACKLIB-IV data sets collapsed into 25 neutron and 21 gamma groups differ up to 23%.