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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.
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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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.
Stan Kaplan
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 137-142
Technical Note | Mixed-Oxide Fuel / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34809
Articles are hosted by Taylor and Francis Online.
This paper is inspired by the recent work of Theofanous et al on the risk of liner failure in Mark-I containments. In that work, the authors presented a probabilistic framework and methodology for dealing with uncertainties surrounding “Level 2,” i.e., post-core-melt phenomena in nuclear plants. In so doing, they have advanced the state of the art of risk assessment and decision making in regard to such phenomena. The key ideas in this framework and methodology have application, of course, beyond Level 2 phenomena. The purposes of the present paper are to abstract and lift out these key ideas so that they can be seen more clearly and to place them in context along with similar ideas used elsewhere, particularly in seismic risk assessment and in the treatment of through-wall cracking and pressurized thermal shock transients. The author hopes, in this way, to clear up confusion and to advance the cause of consistency in the use of the words “probability,” “uncertainty,” “frequency,” “variability,” “randomness,” etc.