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BWXT’s Centrifuge Manufacturing Development Facility opens in Oak Ridge
BWX Technologies announced on January 26 that it has begun operating its Centrifuge Manufacturing Development Facility in Oak Ridge, Tenn., with the purpose of reestablishing a domestic uranium enrichment capability to meet U.S. national security needs. The facility is part of a program funded by the Department of Energy’s National Nuclear Security Administration to supply enriched uranium for defense needs.
Lance Davis, Ralph Hania, Dennis Boomstra, Dillon Rossouw, Florence Charpin-Jacobs, Jan Uhlir, Martin Maracek, Helmut Beckers, Sebastian Riedel
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 633-646
Technical Paper | doi.org/10.1080/00295639.2022.2129951
Articles are hosted by Taylor and Francis Online.
Radiolytic fluorine gas production at temperatures of 40°C to 60°C was investigated for the fluoride salts LiF, BeF2, UF4, ThF4, and 71.7LiF-16BeF2-12.3UF4 (FliBe-UF4) by gamma irradiation of powdered samples using spent fuel elements from the High Flux Reactor (HFR) Petten as the irradiation source; work of a similar nature was previously performed at Oak Ridge National Laboratory in the period 1965 to 1995. Gamma irradiation was conducted for just over 41 days, with total absorbed gamma dose ranging from ~45 MGy for the lightest salts to ~170 MGy for ThF4 and UF4. By measuring the gas pressure within salt-filled capsules during irradiation, it was possible to quantify radiolytic gas production for all salt samples except UF4. Production rates are reported as the salt G-values, measured as number of fluorine molecules produced per 100 eV of energy absorbed (molecules F2/100 eV). The G-values of the salts were found to be G(LiF) ~0.004, G(BeF2) ~0.009, G(ThF4) ~0.021, and G(FLiBe-UF4) ~0.005.