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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!
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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.
K. A. Werley, C. G. Bathke, R. A. Krakowski, R. L. Miller, J. N. DiMarco
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1266-1271
Result of Large Experiment and Plasma Engineering | doi.org/10.13182/FST91-A29515
Articles are hosted by Taylor and Francis Online.
Essential to the achievement of economically compact fusion power cores is the radiation of a large fraction of the plasma heating power uniformly to the first wall, thereby assuring adequate longevity of the divertor impurity control system. The radiation of significant fractions of the heating power from the beta-limited core-plasma region in an RFP, however, requires a corresponding increase in the quality of (non-radiative) confinement. It is shown that radiating ≳ 70% of the total heating power from the core plasma of the TITAN compact reversed-field-pinch (RFP) reactor is possible with non-radiative confinement times that are a large factor (> 15) below classical confinement predictions and are within the present scaling relation based upon extrapolations of the existing RFP transport database. By comparison, the confinement in the ARIES-I tokamak reactor is within a factor of 2 of neo-classical predictions.