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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
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.
W. Schenk, A. Naoumidis
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 228-233
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32321
Articles are hosted by Taylor and Francis Online.
In the course of the German high-temperature gas-cooled reactor Prototype Nuclear Process Heat Safety Program, the behavior of unirradiated fuel particles as well as of irradiated fuel elements at high temperatures was investigated. Unirradiated fuel particles with different designs have been heated to temperatures of 2500°C. Different particle types showed a different high-temperature behavior. While the Biso Thorium High-Temperature Reactor (THTR) type was the most resistant one, Triso particles failed at lower temperatures because of the SiC decomposition. Whole fuel spheres with Biso particles, irradiated in a pebble-bed reactor, were also heated up to 2500°C THTR fuel elements with a burnup of 12 to 16% FIMA (120 000 to 160 000 MWd/t) showed excellent behavior up to 2400°C. At 2500°C, the particles failed in significant numbers after some hours. While rare gas nuclides and iodine were retained in the coated particles as long as the coatings remained intact, the release of some solid fission products, especially cesium, was high above 2000°C.
