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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.
Doron Gal, David Saphier, Ezra Elias
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 64-76
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34568
Articles are hosted by Taylor and Francis Online.
A U-tube steam generator (UTSG) module for the Dynamic Simulator for Nuclear Power Plants is developed. This module is to be used in the simulation of pressurized water reactor (PWR) transients and parametric studies, and it is based on a movable boundary model in which the volumes of the various control volumes are dynamic variables. The UTSG is divided into ten control volumes with movable boundaries between them. The intensive mass and energy balance equations are solved in each control volume, while two integral momentum equations are solved for the primary and secondary flow paths. A homogeneous equilibrium model is assumed in the boiling region. The UTSG model was included in a detailed simulation of the Trojan PWR primary loop. A small loss-of-coolant accident event resulting from a stuck open relief valve transient is presented as an application example.