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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
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.