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- W4313821820 abstract "development. The objectives of these analyses were (1) to identify potential sources of bias in fluoride salt-cooled and salt-fueled reactor simulations resulting from cross section uncertainties, and (2) to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a final report on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. In the future, these S/U analyses could be used to inform the design of additional FLiBe-based experiments using the salt from MSRE. The key finding of this work is that, for both solid and liquid fueled fluoride salt reactors, radiative capture in 7Li is the most significant contributor to potential bias in neutronics calculations within the FLiBe salt." @default.
- W4313821820 created "2023-01-09" @default.
- W4313821820 creator A5031710677 @default.
- W4313821820 date "1968-05-15" @default.
- W4313821820 modified "2023-09-27" @default.
- W4313821820 title "MSRE Book Uranium Inventories at Recovery of 235 Fuel Charge" @default.
- W4313821820 doi "https://doi.org/10.2172/1908057" @default.
- W4313821820 hasPublicationYear "1968" @default.
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