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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Work advances on X-energy’s TRISO fuel fabrication facility
Small modular reactor developer X-energy, together with its fuel-developing subsidiary TRISO-X, has selected Clark Construction Group to finish the building construction phase of its advanced nuclear fuel fabrication facility, known as TX-1, in Oak Ridge, Tenn. It will be the first of two Oak Ridge facilities built to manufacture the company’s TRISO fuel for use in its Xe-100 SMR. The initial deployment of the Xe-100 will be at Dow Chemical Company’s UCC Seadrift Operations manufacturing site on Texas’s Gulf Coast.
J. M. Chapman, C. M. Huddleston
Nuclear Science and Engineering | Volume 25 | Number 1 | May 1966 | Pages 66-74
Technical Paper | doi.org/10.13182/NSE66-A17502
Articles are hosted by Taylor and Francis Online.
Methods are outlined for computer calculation of first- and second-order contributions to gamma-ray dose rates in two-legged rectangular concrete ducts of personnel shelters. Four computer programs, based on values of differential dose albedo derived from Monte Carlo calculations, are used to calculate corner-lip inscattering, backscattering from surfaces visible to both source and detector, and combinations of these two scattering events. The first program computes the dose contribution from corner-lip inscatter and from combinations of corner-lip penetration and wall backscatter. The second calculates first-order backscatter from the basic scattering areas in the corner of the duct. The third computes the second-order backscatter contribution from two successive backscatters from the duct walls. The final program calculates the contribution due to combinations of one wall backscatter and one corner-lip inscatter. The results of the calculations are compared with experimental results obtained by several investigators. The experimental studies used 11 × 11-in., 3 × 3-ft, and 6 × 6-ft ducts; the gamma-ray sources were, variously, 198Au, 137Cs, 60Co, and 24Na. Since the difference between calculated and measured values of gamma-ray dose in the second leg is generally less than 30%, results obtained by calculation can be used to predict the attenuation factors of two-legged concrete ducts and entranceways leading into personnel shelters with an expected error of less than 30%.