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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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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.”
William T. Sha
Nuclear Science and Engineering | Volume 25 | Number 4 | August 1966 | Pages 413-421
Technical Paper | doi.org/10.13182/NSE66-A18562
Articles are hosted by Taylor and Francis Online.
A one-dimensional noniterative method for calculating the fast- and thermal-neutron flux distribution, effective neutron multiplication factor, power density, enthalpy profile, water density distribution, and steam void map of a light-water moderated reactor core is presented and programmed as a computer code — ANDREA. In this method, the spatial dependence of the neutron spectrum is accounted for explicitly. The method outlined in this paper can be used as one of the design tools for pressurized water reactor (PWR) cores as well as for boiling water reactors (BWR). The novelty of this method lies in its noniterative mathematical formulation which takes into account the nuclear-thermal interaction in a reactor channel. Fission density is directly related to heat generation and heat generation causes density changes in the coolant with subsequent formation of steam voids. The method described here is based on the fact that the above relationships are interdependent. As a result of this noniterative formulation, a significant amount of computer time is saved. Finally, it is to be noted that the method presented in this paper is primarily intended for the analysis of large power reactors.