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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
A. W. Molvik, R. W. Moir, D. D. Ryutov, T. C. Simonen
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 70-76
Fusion | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13399
Articles are hosted by Taylor and Francis Online.
Axisymmetric mirrors can be MHD-stabilized by end losses. Neutral-beam-sustained operation to ~0.6, and Te~0.2 keV, with 5 ms 5 MW neutral beams on the Gas Dynamic Trap (GDT) has been demonstrated at the Budker Institute in Novosibirsk, Russia. Applications of this concept can reduce risks in the fusion program. A GDT-scale facility could test plasma-material interactions (PMI) at up to 400 MW/m2 and 5 s pulse duration for divertor development. Extrapolation of the GDT to a Dynamic Trap Neutron Source, DTNS, provides a DT-fusion neutron flux of 2 MW/m2 over 1 m2, at a power-plant efficiency of Q ~ 0.07. (A DTNS enables development and testing of materials and sub-component structures, for fusion power plants, MFE or IFE. A DTNS functions regardless of whether the tested components work. These developments would reduce risks for a tokamak Fusion Nuclear Science Facility (FNSF)). Further extrapolation to 0.2 Q 10 single-cell or tandem mirror yields several fusion-fission hybrid applications. Further extension to a pure-fusion axisymmetric-tandem-mirror power plant, requires Q>10. Tandem mirrors demand the use of different stabilization techniques that are not dependent on out-flowing plasma, a number of which have been proposed, and could be experimentally tested on the GDT.