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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
In an international industry, regulators cross the border too
Since nuclear physics works the same in Ontario as it does in Tennessee, the industry has been trying to create a reactor that can be deployed on both sides of the border. Now, the Nuclear Regulatory Commission and the Canadian Nuclear Safety Commission have decided that some of their rulings can cross the border too.
Micheal A. Smith, Richard M. Lell, Gerardo Aliberti, Zhaopeng Zhong, Florent Heidet
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S71-S82
Technical Paper | doi.org/10.1080/00295639.2022.2058845
Articles are hosted by Taylor and Francis Online.
The Versatile Test Reactor (VTR) that is being designed today is heavily reliant upon the Argonne Reactor Codes (ARC) modeling software for predicting the operational performance of the VTR. Given its usage in the VTR, a set of validation cases appropriate for the VTR must be assembled. The measurements taken in ZPPR-15, Experimental Breeder Reactor II (EBR-II), and Fast Flux Test Facility were chosen and analyzed with the ARC software as part of creating the necessary validation basis. The results of the ARC software on the measured data are discussed here, and they demonstrate the accuracy of the ARC software on fast spectrum reactors.
