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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
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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.
T. J. Downar
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 334-340
Technical Note | doi.org/10.13182/NSE93-A24063
Articles are hosted by Taylor and Francis Online.
Depletion perturbation theory was developed within the framework of an advanced hexagonal nodal diffusion method. A similarity transformation method was used to compute the mathematical generalized adjointsfrom the corresponding physical system because it was more convenient to utilize the numerical algorithms and codes developed for solving the real system equations. The methods were implemented using the DIF3D code for the flux solutions and were applied to a sample problem using a hexagonal geometry lattice. In all cases, there was good agreement between the results of direct subtraction and the depletion sensitivities. This work indicates it is feasible to generate depletion sensitivities within the framework of advanced nodal diffusion methods.