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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Sin Kim, Goon Cherl Park
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 284-294
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2870
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulic field analysis code using the finite element method is developed to analyze the effects of anisotropic turbulent diffusion and secondary flow on turbulent mixing, which is essential to the nuclear fuel performance analysis.In this study a new model of anisotropic eddy viscosity is developed. The representative value of the anisotropic factor is determined from the scale relation that is derived on the basis of the flow pulsation phenomenon. The spatial distribution is deduced qualitatively from well-known experiments. The flow fields calculated by this code are compared with experimental data and show good agreements, and the predicted turbulent mixing rates are successfully compared with the scale relation derived in the authors' previous work.The results show that the isotropic eddy viscosity model underestimates the mixing rate and gives the reverse trend as the gap size reduces, and the secondary flow has a minor effect compared with the anisotropic eddy viscosity in the turbulent mixing process. Although the mixing phenomenon of the flow pulsation is a convective process, it can be simulated only by the anisotropic model.