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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.
Jerzy Mackiewicz
Nuclear Science and Engineering | Volume 99 | Number 2 | June 1988 | Pages 99-108
Technical Paper | doi.org/10.13182/NSE88-A23550
Articles are hosted by Taylor and Francis Online.
A new nodal approach for global reactor core calculations is described, in which local weighted residual procedure equations are consistently embedded into a classical nodal scheme without the necessity of a transverse leakage fitting approximation. The equations derived are formulated for arbitrary node geometry and a wide class of base functions. Simplicity and efficiency of the final relations are assured for regularly shaped nodes by means of symmetry considerations. Application to hexagonal geometry of nodes is discussed. Numerical results for few-group steady-state problems in hexagonal geometry prove highly accurate, comparable to analytic codes, and better with respect to computational efficiency.