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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
Masato Uchita, Takayuki Miyagawa, Koji Dozaki (JAPC), Yoshitaka Chikazawa, Shigenobu Kubo, Hiroki Hayafune (JAEA), Tetsuji Suzuno, Tsuyoshi Fukasawa, Yoshio Kamishima (Mitsubishi FBR Systems, Inc.), Satoshi Fujita (Tokyo Denki Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 380-386
The pool-type reactor encloses primary pumps and IHXs located around the core barrel in a reactor vessel. Consequently, the reactor vessel diameter tends to be larger than that of loop-type reactor. From the viewpoint of commercialization in the future, the vessel diameter and its weight including sodium coolant will increase further. Moreover, the seismic loading conditions imposed on design works of the SFR concept are very severe for large vessel. For the heavy weight large vessel under severe seismic conditions, the buckling evaluation on the cylindrical part of the vessel is significant for a feasibility study. In this paper, the prospects are described in terms of seismic design to prevent buckling of the reactor vessel based on parameter studies with diameters of the vessel. In addition, the seismic isolation device which will be effective as a countermeasure is proposed in order to secure a margin against buckling of a large reactor vessel.