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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.
Alexander I. Livshits, Yuji Hatano, Kuniaki Watanabe
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 882-886
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22711
Articles are hosted by Taylor and Francis Online.
Superpermeable membranes based on Group Va metals can be applied in fusion devices for a short way separation of D/T mixtures from He, for an active control of particle fluxes and as a general-purpose D/T pump that may be used in particularly in tritium handling systems. Superpermeable membranes being used for D/T separation from helium are able to drastically reduce the tritium load on the He pump (cryopump), while tritium accumulation in the membrane itself does not exceed a few g for a machine of ITER scale. A possible way to decrease the tritium inventory in the membrane is to combine a higher dissociative barrier at the upstream surface with the operation at higher temperature. Compression of permeating D/T attainable with superpermeable membranes is totally determined by the sticking coefficient of thermal hydrogen molecules at the upstream surface. The degree of compression has a significant effect on the tritium inventory and the inventory dependence on the state of the downstream surface.1 Permanent address: Bonch-Bruyevich University, 61 Moika, St. Petersburg 191186, Russia