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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Kazuo Takino, Kazuteru Sugino, Kenji Yokoyama (JAEA), Tomoyuki Jin (NESI Inc.), Shigeo Ohki (JAEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1214-1220
Since next-generation fast reactors aim to achieve a higher core discharge burn-up than that of the conventional ones, nuclear design methods need to refine. In this study, we investigated the effect that the analysis conditions exhibit on the accuracy of estimations of the burn-up nuclear characteristics of next-generation fast reactors. Suitable analysis schemes and conditions that maximize the estimation accuracy, while maintaining a low computational cost, were investigated in this study.
We performed core burn-up survey calculations under several analysis conditions. In the survey calculations, we calculated the criticality, burn-up reactivity, control rod worth, breeding ratio, assembly-wise power distribution, maximum linear heat rate, sodium void reactivity, and Doppler coefficient for the equilibrium operation cycles. The accuracy of the low-cost calculations was evaluated by measuring the agreements with the referential detailed conditions.