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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Paride A. Ombrellaro, David L. Johnson
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 180-200
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32734
Articles are hosted by Taylor and Francis Online.
A method of calculating the neutron source strength in irradiated fast flux test facility (FFTF) fuel has been developed. This method has been used to perform calculations in support of the reactivity monitoring of the FFTF reactor by the modified source multiplication method during refueling operations. Isotope buildup and depletion in FFTF fuel as a function of irradiation were evaluated with the ORIGEN and ALCHEMY codes using updated libraries of effective cross sections and half-lives. More accurate evaluations of isotopic density changes in fuel than previously possible were made at the Hanford Engineering Development Laboratory using the ENDF/B-V cross sections. Libraries of oneenergy-group effective cross sections for capture, fission, and (n,2n) reactions were developed by spectrum averaging 12-energy-group cross sections with typical 12-energy-group spectra in the inner and outer driver regions of FFTF Cores 1 and 2 at the beginning of life, the beginning of cycle 4, and end of cycle 4. The calculational results of isotope depletion and buildup for inner driver and outer driver fuel were used with recently evaluated neutron yields for spontaneous fission and (α,n) reactions. These provided for more accurate neutron source level evaluations. Neutron source strengths in FFTF cores 1 and 2 fuels, as a function of irradiation, were calculated and used in reactivity calculations for a sequence of core configurations representative of a typical FFTF refueling plan. The results of such calculations are presented.