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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.
S. I. Bhuiyan, R. W. Roussin, J. L. Lucius, J. H. Marable, D. E. Bartine
Nuclear Science and Engineering | Volume 93 | Number 3 | July 1986 | Pages 313-317
Technical Note | doi.org/10.13182/NSE86-A17760
Articles are hosted by Taylor and Francis Online.
Three models, a linear, exponential or BEST, and a power model, developed using sensitivity theory to predict deep-penetration neutron transport in practical shielding problems, have been generalized into a common expression. One can obtain any of the above three models from this generalized expression simply by choosing the proper index parameters. Subsequently, a scheme for implementation of this into a computer code was adopted in “SENATOR.” SENATOR replaces the SENTINEL module of the Oak Ridge National Laboratory (ORNL) FORSS system. The supporting data bases (i.e., the sensitivity profile) and the Fortran code, along with some utility programs, are assembled in a package identified as CONSENT and can be obtained through the Radiation Shielding Information Center at ORNL.