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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.
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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
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.
K. A. Werley, C. G. Bathke, R. A. Krakowski, R. L. Miller, J. N. DiMarco
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1266-1271
Result of Large Experiment and Plasma Engineering | doi.org/10.13182/FST91-A29515
Articles are hosted by Taylor and Francis Online.
Essential to the achievement of economically compact fusion power cores is the radiation of a large fraction of the plasma heating power uniformly to the first wall, thereby assuring adequate longevity of the divertor impurity control system. The radiation of significant fractions of the heating power from the beta-limited core-plasma region in an RFP, however, requires a corresponding increase in the quality of (non-radiative) confinement. It is shown that radiating ≳ 70% of the total heating power from the core plasma of the TITAN compact reversed-field-pinch (RFP) reactor is possible with non-radiative confinement times that are a large factor (> 15) below classical confinement predictions and are within the present scaling relation based upon extrapolations of the existing RFP transport database. By comparison, the confinement in the ARIES-I tokamak reactor is within a factor of 2 of neo-classical predictions.