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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.
P. Vontobel, S. Pelloni
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 298-301
Technical Note | doi.org/10.13182/NSE89-A23618
Articles are hosted by Taylor and Francis Online.
Using the NJOY nuclear data processing system, three multigroup MATXS-formatted nuclear data libraries were generated based on the European datafiles JEF-1 and EFF-1, After processing with TRAMIX, TRANSX, or TRANSX-CTR, these libraries can be read into most transport and diffusion codes. For the neutron analysis of gas-cooled or water-moderated thermal reactor systems (including high converter pressurized water reactors), a 70-group WIMS-BOXER structured library was generated. A general-purpose fine-group library in 308 groups is provided for thermal as well as for fast reactor systems. A coupled 175 neutron/42 photon-group library in VITAMIN-J structure was created for the analysis of shielding problems and fusion blanket design. The three MATXS files can be requested from the Nuclear Energy Agency Data Bank.
