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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.
V. Ya. Goloborod'ko, V. V. Lutsenko, S. N. Reznik, V. A. Yavorskij
Fusion Science and Technology | Volume 27 | Number 3 | May 1995 | Pages 292-297
Technical Paper | Plasma Engineering | doi.org/10.13182/FST95-A30391
Articles are hosted by Taylor and Francis Online.
Three-dimensional Fokker-Planck simulation of collisional losses of mega-electron-volt fusion products in axisymmetric tokamaks with plasma currents I < 2 MA is carried out. The calculations take into account both loss due to radial diffusion and loss caused by pitch-angle scattering in the first-orbit loss region in velocity space. Collisional losses of deuterium-deuterium (D-D) fusion products in the energy range 0.5 ≤ ε/ε0 ≤ 1 (where ε0 is the birth energy) are found to be increased with plasma current and comparable to a first-orbit loss at I > 1.5 MA. The loss mechanism considered may be responsible for the observed experimentally delayed losses of D-D fusion products in the Tokamak Fusion Test Reactor (TFTR). The dependencies of collisional losses on plasma current, effective charge number of the plasma (Zeff), and aspect ratio are investigated. The distributions of escaped ions over pitch angles, energies, and poloidal angles are evaluated. The fraction of collisionally lost fast fusion products is shown to scale like (ν⊥/νs)0.6 or (here ν⊥ and νs are characteristic collision rates of pitch-angle scattering and slowing down, respectively). The approach used may be considered as an alternative to the approach based on Monte Carlo modeling of scattering and can serve as a validity check of the latter.