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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Masabumi Nishikawa, Kazuya Furuichi, Hiroki Takata
Fusion Science and Technology | Volume 50 | Number 4 | November 2006 | Pages 521-527
Technical Paper | doi.org/10.13182/FST06-A1275
Articles are hosted by Taylor and Francis Online.
Concrete walls play the role not only of the structural material but also of the final barrier of a multiconfinement system of tritium in a fusion reactor or a tritium-handling facility. Therefore, it is required that the behavior of tritium in the concrete materials be clarified to certify the radiation safety of a fusion reactor. The diffusion coefficient of hydrogen in cement paste is obtained by using the permeation experiment in this study, and it is found that the diffusion coefficient of hydrogen in the cement paste is only one order magnitude smaller than the diffusion coefficient of hydrogen in air. Calculation using the diffusion coefficient obtained in this study indicates that the gaseous tritium, HT or T2, can permeate rather rapidly to the outside through the concrete wall of a tritium-handling facility. This calculation implies that installation of a tritium recovery system with proper decontamination performance is required to minimize the tritium transfer to the outer environment.