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.
G. Sdouz
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 162-168
Technical Paper | doi.org/10.13182/NSE88-A28496
Articles are hosted by Taylor and Francis Online.
To ensure an optimal application of fuel behavior codes, international standard problems (ISPs) are performed by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. Calculations performed with complex fuel analysis codes consume considerable implementation and running times. To avoid the application of these codes, a fast-running deformation code was extended to a fuel behavior code called BALO-2A. With this code, two standard problems were performed: ISP-14, which is based on the bundle experiment REBEKA-6, and ISP-19, performed at the Phebus facility. In each standard problem, different methods have to be applied to obtain boundary conditions and input values. The results indicate that BALO-2A simulates fuel behavior under loss-of-coolant accident conditions quite well.
