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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.