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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.
P. L. Viollet, J. P. Benque, J. Goussebaile
Nuclear Science and Engineering | Volume 84 | Number 4 | August 1983 | Pages 350-372
Technical Paper | doi.org/10.13182/NSE83-A15456
Articles are hosted by Taylor and Francis Online.
Finite difference numerical methods are available for the computation of unsteady non-isothermal flows with possibly strong buoyancy effects or head loss terms. The algorithm uses either velocity-pressure or velocity-stream-function formulations. The treatment of advective terms involves the method of characteristics. Arbitrary non-orthogonal curvilinear grids may be used, and turbulence is modeled by means of a k-ϵ eddy viscosity model. Two examples of application to liquid-metal fast breeder reactor thermal analysis are: 1. hot plenum flow in a pool-type vessel during flow and thermal transients, 2. unsteady flow in a pipe resulting from an inlet temperature change with a very low flow rate. For both cases, comparisons with experimental studies and applications to real reactors are shown.