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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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June 2025
Nuclear Technology
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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.
R. D. Mosteller*, Warren M. Andrews, Odelli Ozer, W. J. Eich
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 192-197
Technical Note | Fuel Cycle | doi.org/10.13182/NT79-A32252
Articles are hosted by Taylor and Francis Online.
The adequacy of the Advanced Recycle Methodology Program for predicting isotopic ratios as a function of exposure is determined for a light water reactor of modern design. For the first time, the capabilities of a two-dimensional multigroup transport theory code have been applied to the calculation of isotopic parameters for a commercial U.S. pressurized water reactor. The calculated results are found to be in satisfactory agreement with benchmark measurements. However, captures in seem to be underpredicted when ENDF/B-IV (or ENDF/B-III) resonance parameters for the 1.056-eV resonance are used in the calculations.
