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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.
L. M. Gomes, P. N. Stevens
Nuclear Science and Engineering | Volume 114 | Number 3 | July 1993 | Pages 228-237
Technical Paper | doi.org/10.13182/NSE93-A24036
Articles are hosted by Taylor and Francis Online.
Ray effects, an inherent problem in the formulation of the discrete ordinates approximation to the transport equation, are studied. In particular, the effectiveness of using Monte Carlo procedures to generate a first or second collision source is investigated. Monte Carlo procedures provide a general methodology that can be applied to the discrete ordinates solution of complex problems in either two-dimensional or three-dimensional geometries for which ray effects are likely to occur. The Monte Carlo method, which is intrinsically free of ray effects, performs the transport of the source particle to the first collision sites, at which estimates for the uncollided fluxes are made. The uncollided fluxes are then used to compute the first collided fluxes. The uncollided, collided, or first collided fluxes are calculated as first or second collision scattering sources in a format suitable for input into the DORT two-dimensional and TORT three-dimensional discrete ordinates codes. The computational time and precision requirements of the Monte Carlo calculation are analyzed. The results show that significant improvements are achieved in the solution of test problems when using the estimated first collision source and that ray effects are virtually eliminated when using the estimated second collision source.