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Division Spotlight
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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Latest News
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.
Edmund T. Rumble, III, William E. Kastenberg
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 172-187
Technical Paper | doi.org/10.13182/NSE72-A35505
Articles are hosted by Taylor and Francis Online.
Several nonlinear space-time reactor models are studied by employing modal analysis. Eigenfunction modes resulting from the solution of Sturm-Liouville equations satisfying the appropriate linear portion of the neutron diffusion equation are chosen. These modes form a complete, orthogonal set and are convenient to calculate numerically. Examples where coefficients and time constants are representative of present reactor design are studied. The work is focused on space-dependent feedback and local step and ramp reactivity insertions. The large difference in the neutronic and thermal-hydraulic time constants gives rise to computational difficulties. This difficulty, characteristic of “stiff systems” was minimized by use of a rational extrapolation technique to solve the resultant equations.