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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Han Eol Park, Seok Bin Seo, In Cheol Bang (UNIST)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 479-484
Nu-HOPE (Nuclear-Highly Optimized Prandtl number Experiment facility) is a newly built facility in UNIST to simulate molten salt reactor. Due to the high-temperature corrosion and toxicity issue, the heat transfer phenomena of molten salt are studied under similarity technique with high-Prandtl number simulant fluid. 12-meter-high Nu-HOPE was designed for the study of both natural and forced circulation of high-Prandtl number fluid. Experimental results of natural and forced circulation can give the evaluation of heat transfer characteristics and fluid stability model for the simulant molten salt. In this paper, design of Nu-HOPE based on numerical approach to developing heat transfer model of high-Prandtl number fluid is suggested.
