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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Ken Amano, Kotaro Inoue
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 409-414
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33396
Articles are hosted by Taylor and Francis Online.
An analytical model describing pressure fluctuation of turbulent flow in liquid-metal fast breeder reactor (LMFBR) fuel assemblies has been proposed, and the oscillation amplitude of a fuel pin thus caused has been calculated. In the treatment, the statistical model for pressure fluctuation in stable turbulent flow was assumed, and the fluctuation was estimated from pressure loss of flow and velocity gradient. The vibration amplitude was calculated by solving a Langevin equation. According to the comparison of the calculated results with experimental data, this model realistically describes the fuel pin vibration in LMFBR fuel assemblies.
