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Division Spotlight
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
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.
K. Nam et al.
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 131-135
ITER | 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-A18067
Articles are hosted by Taylor and Francis Online.
This paper describes the fabrication of removable panel for ITER cryostat thermal shield (CTS) and its conduction cooling test at cryogenic temperature. Two kinds of full-scale mock-ups of the removable panels have been developed, depending on different thermal conduction designs. Passive cooling characteristics of the mock-ups are investigated with the measured data of temperature jump at the joint and maximum temperature at the panel. The passive cooling of panel with copper insertion satisfies the design requirement of temperature jump (< 3 K), even though the heat load condition in the cooling test is more severe than the design condition of CTS. It is clearly demonstrated that the copper strips bonded on the panel attenuate the temperature gradient of the panel. Different thermal behaviors at the joint are also found for the two mock-ups.