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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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Myunghwa Shim, Hongsuk Chung, Hiroshi Yoshida, Haksoo Jin, Min Ho Chang, Sei-Hun Yun, Seungyon Cho
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 856-860
Tritium Breeding | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-13
Articles are hosted by Taylor and Francis Online.
We are developing an innovative ZrCo hydride bed design, which is characterized by a large cylindrical filter, very thin cylindrical metal hydride powder packed layer, and large relative heating area per unit weight of ZrCo powder for ITER fuel cycle application. To validate this design concept, two ZrCo bed models each loaded with 127 g of ZrCo were tested by using H2 gas. In the first model, ZrCo powder was packed into the 3 mm gap between the filter cylinder and the vessel, and mold heater elements were attached to the outer surface of the vessel. The second model consisted of a layer of ZrCo powder packing (7 mm thickness), coiled cable heaters attached independently to the outer surface of the primary vessel and the inner surface of the filter cylinder. This paper presents detailed design features of the ZrCo bed models, and test results of the beds performances, i.e., temperature transient of the ZrCo packed bed during fast heating, hydriding rate up to 90-99% recovery, and 90-98% delivery fraction.