ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
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.”
Adam G. Nelson, Nicolas Martin, Alisha Kasam-Griffith, Zhiwen Xu, Florent Heidet
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S63-S70
Technical Paper | doi.org/10.1080/00295639.2022.2035181
Articles are hosted by Taylor and Francis Online.
The Versatile Test Reactor (VTR) is being developed to provide a flexible source of neutrons for the accelerated testing of materials. To support this flexibility, the design must be informed by uncertainty assessment that defensibly provides the needed margin. This paper provides an overview of the VTR Program’s approach to the generation and application of uncertainties in the reactor core design process as it relates to this goal. As the uncertainty assessment is still in progress, this paper not only provides an example of how uncertainty has been factored into the early stages of design but also provides findings from sensitivity studies that will form the basis of future uncertainty work.