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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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Kyung Mo Kim, In Guk Kim, Yeong Shin Jeong, In Cheol Bang (UNIST)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1161-1167
Guarantee of the diversity by installation of additional safety system, having different working principle from the existing systems, could mitigate the suggested issues on the passive safety systems. Hybrid control rod-heat pipe, which is a passive decay heat removal device combining the functions of heat pipe and control rod, was proposed by UNIST in Republic of Korea as a passive safety system improving the diversity of passive safety in small modular reactors. It was designed to perform both functions of decay heat removal and reactivity control simultaneously. From the performance analysis, it was found that the designed hybrid control rod has sufficient decay heat removal capacity and reactivity worth. Additionally, hydraulic control rod drive mechanism, which controls the movement of control rod by hydraulic resistance, was designed to achieve fully-passive operation of the hybrid control rods eliminating the malfunction of CRDM owing to electromagnetic signal error. Based on the feasibility study for the concept of hybrid control rod and hydraulic control rod drive mechanism, detailed design of passive in-core cooling system (PINCs) for SMR consisting of hybrid control rods, hydraulic control rod drive mechanism, and heat sinks, was constructed considering the operations of PINCs during normal and accident conditions of reactor.