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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.
Shu-Chien Yung, Norman P. Wilburn
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 23-38
Technical Paper | Reactor | doi.org/10.13182/NT80-A32409
Articles are hosted by Taylor and Francis Online.
Intrasubassembly incoherencies affecting the fuel pin failure pattern within a fast test reactor (FTR) subassembly during an unprotected transient overpower/hypothetical core disruptive accident have been investigated using the COBRA-III/MELT code. Two dominant intrasubassembly incoherencies in an FTR subassembly were studied, namely, (a) the hydraulic effect, or the variation in pin-power-to-effective-coolant ratio between pins in the inner region and those in the outer region of the sub-assembly, and (b) the power skew, or variation in pinwise power density for pins throughout the subassembly. The hydraulic effect study concluded that a one-pin representation as used in SAS3A and MELT-IIIA does not represent the fuel pin failure characteristic of any pin in the inner or outer region of the subassembly, but only the failure characteristic of some hypothetical “average” pin, which generally fails much later than most of the pins that actually would fail in the subassembly during the postulated accident. From the power-skew study, it was found that the domain of fuel pin failure times is further widened by the power-skew incoherency. A widened domain of failure times can alleviate molten fuel/coolant interaction by not squirting molten fuel into all coolant subchannels simultaneously. The power skew also produces an eccentric failure pattern within the subassembly that reduces the possibility of a complete fuel blockage.