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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.
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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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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.
H. B. Choi, T. J. Downar
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 205-213
Technical Note | doi.org/10.13182/NSE92-A23934
Articles are hosted by Taylor and Francis Online.
Depletion perturbation theory has been extended to the closed nuclear fuel cycle, and methods have been developed for computing the constrained sensitivities that account for fuel reprocessing and fabrication. An iterative method was developed to solve the sensitivity equations and applied to the closed fuel cycle of the Integral Fast Reactor (IFR). The sensitivities computed using the method were in good agreement with sensitivities from direct subtraction of perturbed and unperturbed depletion calculations. The closed fuel cycle sensitivities were also compared with the sensitivities for the open fuel cycle without reprocessing. The closed fuel cycle sensitivities were found to be larger, particularly for isotopes higher up the burnup chain. These results indicate this work would have particular importance for the analysis of advanced reactor designs with closed fuel cycles, such as the IFR. The methods developed here will facilitate accurate and efficient sensitivity studies of such reactors.