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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
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.”
Samir M. Sami, C. H. Le
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 7-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33947
Articles are hosted by Taylor and Francis Online.
A dynamic void quality perturbation model has been developed to improve the capabilities of the NUFREQ code with respect to local void perturbation calculations. The present model calculates the local void perturbation in terms of the local quality perturbation, the dynamic drift flux parameters, and the transient time. In addition, the model evaluates the void reactivity feedback and the boiling channel nuclear reactor feedback. Depending on the flow regime, this model can predict the local void fraction perturbation in horizontal (CANDU reactors) and vertical channels (light water reactors). Numerical results revealed that this model enhanced the capabilities of the NUFREQ code and improved its accuracy in predicting the lower natural frequency as well as the system frequency response at higher frequencies.
