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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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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.
M. J. Haire, L. R. Zumwalt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 91-97
Technical Paper | doi.org/10.13182/NSE73-A23232
Articles are hosted by Taylor and Francis Online.
To determine fission product-graphite sorption behavior, an experimental and analytical study was conducted to obtain a model which would predict the vapor pressures of mixtures of sorbed fission product metals as a function of temperature and composition.The graphite sorbents studied were SP-1C, a very pure natural flake graphite, and TS-688, a typical needle-coke nuclear-grade graphite. Cesium and rubidium tagged with 137Cs and 86Rb were the sorbates, and the pseudo-isopiestic method was used to determine sorbate concentrations as a function of temperature and vapor pressure. Three models were examined for their capability in predicting binary mixed sorption behavior.Experiments showed the following: (a) The vapor pressure of a species varies inversely with the fraction of total sorbate metal present at a given sorbate concentration and temperature; (b) thermodynamic and FREVAP models were the most successful in the prediction of binary sorption behavior from single component isotherm data. It is concluded that if the departure from ideal adsorption behavior is not known, either model may be used in the calculation of fission product release.