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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.
E. E. Lewis
Nuclear Science and Engineering | Volume 102 | Number 2 | June 1989 | Pages 140-152
Technical Paper | doi.org/10.13182/NSE89-A23639
Articles are hosted by Taylor and Francis Online.
Variational nodal methods for neutron transport are modified to reduce the angular coupling between spatial nodes without a commensurate loss of accuracy. In both one and two dimensions, the interface conditions of the variational principle allow near Pn accuracy to be obtained with only Pn−2 interface coupling. As a result, the dimension of the nodal response matrix is reduced by a factor of 2, and the number of arithmetic operations required for solution by a factor of 4. In the small spatial mesh limit, the resulting Pn, n−2 approximation retains accuracy near the Pn approximation used within the node rather than reverting to the Pn−2 interface approximation. Two-dimensional P3,1 transport calculations demonstrate that the variational nodal approximations are not subject to the flux depression suffered by other interface current nodal transport methods in problems dominated by streaming diagonal to the coordinate directions.