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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!
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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.
M. Gholampour, K. N. Proskouriakov
Nuclear Science and Engineering | Volume 159 | Number 3 | July 2008 | Pages 311-320
Technical Paper | doi.org/10.13182/NSE159-311
Articles are hosted by Taylor and Francis Online.
The goal of this research is to study the coolant parameter fluctuations in the operation mode and start-up period of a nuclear power plant (NPP) with a VVER-1000 water cooled-water moderated power reactor. The coolant pressure pulsations and vibrodynamic processes of the equipment were studied. A new systematic analysis of flow pulsations has been worked out.The measurement results of coolant parameter fluctuations in Unit 1 of the Volgodonskaya NPP are presented. The results of this research are to be utilized for the coolant analysis and detection of the processes that had not been covered in the project documentation but may affect the equipment reliability.