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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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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.
P. E. Labeau, Z. Ould Amar
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 146-157
Technical Paper | doi.org/10.13182/NSE97-A24468
Articles are hosted by Taylor and Francis Online.
Monte Carlo games especially designed for probabilistic dynamics problems have been shown to be very efficient for the calculation of a pressurized water reactor (PWR) pressurizer unreliability. However, these methods rely on the implicit hypothesis that transition rates and probabilities, as well as control means response times, can be precisely determined. But reality is different: Because of a lack of knowledge, only crude estimations of transition rates can be obtained. Moreover, control device response times cannot be assumed constant for rapid transients. Therefore, considering distributed values of these quantities seems more realistic. Several attempts to take into account these uncertainties, while conserving as many advantages as possible of the high-efficiency simulation techniques, are summarized. The PWR pressurizer application is used to compare the capabilities of the proposed methods.