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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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).
Zhiyao Xing, Eugene Shwageraus (Univ of Cambridge)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 777-786
Prismatic block type Fluoride-salt-cooled High-temperature Reactors (FHRs) can benefit from Advanced Gas-cooled Reactor (AGR) technologies. To provide guidance for future AGR-like FHR design, this paper, based on systematic searches across a wide range of AGR-like assembly models and simplified single pin models, studies the beginning of cycle excess reactivity and coolant temperature coefficients of FHRs with different design parameters and alternative salt coolants. LiF-NaF-KF (FLiNaK) and non-Tritium-producing salt NaF-ZrF4 are studied as coolant options alternative to 2LiF-BeF2 (FLiBe) using unit cell models. The results suggest that the NaF-ZrF4 cooled, UC fuelled single pin models with 40% to 100% salt to graphite mass ratios and pitch to diameter ratios of 4.0 to 4.8 can achieve the best beginning of cycle neutronics performances among all designs options surveyed. While the assembly models and pin cell models capture the same reactor physics phenomena, designing FHR strictly within the physical constraint of AGR configuration limits the designs space and results in poorer neutronics performance comparing with the best performing unit cell models. Greater degrees of freedom could be considered in the future assembly level design process to best capture the desirable neutronics benefits of the recommended single pin designs.