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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.
H.C. No, M. S. Kazimi
Nuclear Science and Engineering | Volume 97 | Number 4 | December 1987 | Pages 327-343
Technical Paper | doi.org/10.13182/NSE87-A23516
Articles are hosted by Taylor and Francis Online.
This work involves the development of physical models for the constitutive relations of a two-fluid, three-dimensional sodium boiling code, THERMIT-6S. Based on a simplified flow regime, namely, concurrent annular flow, constitutive relations for two-phase flow of sodium are derived. The wall heat transfer coefficient is based on momentum-heat transfer analogy and a logarithmic law for liquid film velocity distribution. Mass and energy exchanges are modeled by generalization of the turbulent flux concept. Interfacial drag coefficients are derived for annular flows with entrainment. Code assessment is performed by simulating the W-7b’ test for a low-flow, high-power accident in the liquid-metal fast breeder reactor. While the numerical results for predryout are in good agreement with the data, those for postdryout reveal the need for improvement of the physical models. The benefits of nonhomogeneous, nonequilibrium representation of sodium boiling are studied.