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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Jun 2025
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Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Ross Pivovar, Rebecca Owston
Nuclear Science and Engineering | Volume 197 | Number 4 | April 2023 | Pages 686-702
Computer Code Abstract | doi.org/10.1080/00295639.2022.2126718
Articles are hosted by Taylor and Francis Online.
The features and equations of MixcoatlTM are presented in Part 1 of this two-paper series with no discussion on physics verification. The verification of Mixcoatl specifically for prismatic fuel designs/shell-and-tube–like designs is presented here. Furthermore, conclusions are made on the uncertainties that are extendable to the results of other codes that utilize a one-dimensional (1D) flow assumption with Nusselt correlations. Demonstration of commonly used scenarios for reactor designs is explored, and applicable ranges/deviations from the 1D flow assumption are investigated.