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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Mihály Makai
Nuclear Science and Engineering | Volume 82 | Number 3 | December 1982 | Pages 338-353
Technical Paper | doi.org/10.13182/NSE82-338
Articles are hosted by Taylor and Francis Online.
Solving problems of reactor physics is well developed for typical pressurized water and boiling water reactor geometries but less developed for high-temperature gas-cooled reactor, liquid-metal fast breeder reactor, and WWER (BBP) geometries. Several problems of reactor physics can be formulated in a geometry-independent fashion with the help of symmetry considerations, which allows the solution to be decomposed into eigenfunctions of the symmetry operations. An analytic coarse-mesh solution is derived without resorting to the cross leakage concept. The method is applicable to arbitrary geometries. A second-stage homogenization based on the Bloch theorem is presented. It is shown that the solution of the transport equation can always be made up from a cell problem set (microfunctions) and from an overall solution to the diffusion equation (macrofunction).