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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
Alice Ying, Hongjie Zhang, Joseph Mauricio Garde, Mike Ulrickson
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 309-314
Divertor and High-Heat-Flux Components | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18095
Articles are hosted by Taylor and Francis Online.
The impact of Be tile size on the stress exerted on the CuCrZr heat sink for the ITER EHF finger was examined. The study especially focused on the areas beneath the tiles that are exposed to the high convective heat flux. For reference, in a Be tile size of 50x50x8 mm3, the calculated equivalent strain range using elastic analysis for the path of interest through the side wall of the CuCrZr heat sink resulted in a peak value at the inner wall of ~0.492%. The corresponding fatigue lifetime of the heat sink locally is unacceptably low, 1400 cyclic operations. By using smaller tiles, lower stress amplitudes are observed due to a smaller deformation. In this paper, the total strain range under ITER projected pulsed operating conditions is analyzed for a range of Be tile sizes. The analysis model uses a complete pair of twin fingers as opposed to a sub-model of two tiles. The paper documents the calculated cyclic lifetime of the ITER EHF CuCrZr heat sink with respect to Be tile size and peak heat loads by evaluating the total strain range both from elastic and time independent elasto-plastic analyses for repeated cycle.