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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 337-344
Technical Paper | doi.org/10.13182/NSE73-A26568
Articles are hosted by Taylor and Francis Online.
A theoretical study of the pulsed neutron problem and of steady-state neutron spectra has been made in mixtures of H2O and D2O in the temperature range 253 to 4°K. Mixtures with D2O content of 0, 5, 10, 15, and 20 wt% have been considered. For the pulsed neutron problem the multigroup Boltzmann equation in the diffusion approximation has been diagonalized to obtain asymptotic and transient spectra in assemblies with buckling values ranging from 0 to 0.6 cm-2 at 253, 77, and 21°K. The calculated values of the fundamental mode decay constant in various assemblies of ice at 253°K containing 20% D2O are found to agree very well with the experimental values reported by Salaita.For the steady-state problem, the multigroup inhomogeneous Boltzmann equation in the diffusion approximation has been solved by the matrix inversion method for different mixtures at 253, 77, 21, and 4°K. We show that there is an enhancement of cold neutron flux as the D2O content in ice is gradually increased. As in the case of H2O ice, we find that the mean energy of the neutron distribution goes on decreasing with decrease in ice temperature only as long as the temperature is above about 20°K. No further reduction in the mean energy of the neutron distribution is obtained when the temperature of the mixture is reduced below 21°K. It is shown that at 21°K, ice containing about 10 to 20% D2O is a better cold neutron source than pure H2O ice.