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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
T. Ishida, T. Hayashi, M. Yamada, T. Suzuki, K. Okuno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 926-930
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963057
Articles are hosted by Taylor and Francis Online.
In order to develop the more compact and more cost-effective tritium removal system for the fusion reactor, the new system of using gas separation membrane has been studied in Tritium Process Laboratory (TPD/Japan Atomic Energy Research Institute (JAERI). To apply the scaled polyimide membrane module (hollow filament type) to the secondary confinement system, the basic-tritium recovery performance was summarized as a module itself from N2, air, Ar mixture, and recoveral performance was well demonstrated from existing glovebox (1.4 m3 : GB). The tritium recovery performance of the membrane module was well analyzed as a cross flow model, and removal from actual GB results was well simulated by the stand-alone performance data. Using this membrane module performance, new detritiation system was designed for the secondary confinement (GB).
