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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.
K. L. Sidikman, Richard A. Nebel, James D. Callen
Fusion Science and Technology | Volume 15 | Number 1 | January 1989 | Pages 29-36
Technical Paper | Plasma Engineering | doi.org/10.13182/FST89-A25321
Articles are hosted by Taylor and Francis Online.
Magnetic perturbations caused by field errors may pose a threat to magnetic confinement. They can cause the formation of magnetic islands, which may increase transport. The response of a reversed-field pinch (RFP) plasma to field errors has been calculated numerically. A three-dimensional nonlinear magnetohydrodynamic code was used, with field errors specified as boundary conditions. Two types of field errors were studied: those arising from current flowing in the toroidal field coil set and those arising from induced currents in the conducting shell flowing around holes. Design data from two RFPs at the Los Alamos National Laboratory — ZT-40 (currently operating) and ZT-H (being designed) — were used. Results on the effect of the plasma on the radial field perturbation and on island size are given. The effects of the chosen equilibrium current profile, resistivity, and viscosity are discussed.