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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Min Lee, Chen Tsung Fan
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 43-57
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34702
Articles are hosted by Taylor and Francis Online.
Responses of a large, dry pressurized water reactor (PWR) containment in a station blackout sequence are analyzed with the CONTAIN, MARCH3, and MAAP codes. Results show that the predicted containment responses in a station blackout sequence of these three codes are substantially different. Among these predictions, the MAAP code predicts the highest containment pressure because of the large amount of water made available to quench the debris upon vessel failure. The gradual water boiloff by debris pressurizes the containment. The combustible gas burning models in these codes are briefly described and compared. In a station blackout sequence of a large, dry PWR containment, the discrete burning of combustible gases does not occur in the MAAP calculation because of the predicted high steam concentration. A comparison of the one-cell MARCH3 calculation and the six-cell CONTAIN calculation shows that the burning of combustible gases occurs earlier and has a larger impact on containment pressure in the MARCH3 calculation. For the cases analyzed, the simplified MARCH3 calculations always predict a higher containment pressure than the complicated CONTAIN calculations. The results of the CONTAIN calculation show that combustible gas detonation may occur in a local region of a large, dry PWR containment during a station blackout sequence.
