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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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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.
G.A. Esteban, F. Legarda, L.A. Sedano, A. Perujo
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 948-953
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-A22725
Articles are hosted by Taylor and Francis Online.
An accurate and particular description of isotope effects in hydrogen transport within structural martensitic steels is highly needed in nuclear fusion technology in order to describe the tritium-material interaction on the basis of the properties of the non-radioactive hydrogen isotopes (protium and deuterium). As a result, tritium transport investigation becomes technologically more feasible because a cost-effective radioactive device is not mandatory. Additionally, a precise isotopic description allows differentiating the behaviour of the fuel-components deuterium and tritium within the blanket structures in reactor operation conditions. A time-dependent gas-phase isovolumetric desorption technique has been used to evaluate the isotopic effects in the diffusive transport parameters of hydrogen in an 8% CrWVTa reduced activation martensitic steel in the temperatures range 423 to 892 K and driving pressures from 4·104 to 1·105 Pa. Experiments have been run with both protium and deuterium obtaining their respective transport parameters diffusivity (D), Sieverts' constant (Ks), permeability (Φ), the trap site density (ηt) and the trapping activation energy (Et).