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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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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.
Toshikazu Takeda, Kazuhisa Matsumoto
Nuclear Science and Engineering | Volume 114 | Number 1 | May 1993 | Pages 64-75
Technical Paper | doi.org/10.13182/NSE93-A24015
Articles are hosted by Taylor and Francis Online.
A formula for the uncertainty of core performance parameters based on a combination of the cross-section adjustment and bias factor methods has been derived. The formula is compared with those derived from the cross-section adjustment method and the bias factor method used separately. When the method error correlation is strong between the critical assemblies and a target core, the combined method is superior to the cross-section adjustment method used alone. The combined method is, in general, superior to the bias factor method used alone. Numerical results are presented for the uncertainties of keff, the control rod worth, and the power distribution of a large fast reactor. The combined method yields a smaller uncertainty for the control rod worth calculated in dollar units than the cross-section adjustment method used alone.