ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.”
Cesare Frepoli
Nuclear Science and Engineering | Volume 194 | Number 8 | August-September 2020 | Pages 825-832
Technical Note | doi.org/10.1080/00295639.2020.1753419
Articles are hosted by Taylor and Francis Online.
Integral systems test (IST) facilities, which are sometimes referred to as integral effects tests (IETs), play a key role in the design, assessment, and certification of innovative reactor designs. Data obtained using such facilities have been used to benchmark the best-estimate safety analysis computer codes used to evaluate nuclear plant safety. They have also been used to assess the effectiveness of safety system functions under simulated accident conditions. Scaling analyses are an important component in determining the applicability of an evaluation model for its intended purpose. Evaluation models can only approximate the physical behavior of postulated events on a prototype, and the judgment of their adequacy relies heavily on their capability in predicting IETs that were designed to simulate the events analyzed. With few exceptions, all ISTs are subscale representations of the power plants they are built to represent. As thermal-hydraulic computer codes are benchmarked to an IST database, the most important challenge for the analyst is the development of convincing scaling similarities between the IST and the plant. Unless such rules are clearly identified, it would not be possible to extend conclusions from the assessment of the tools against subscale data to the plant scenario time and geometry scales.