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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
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.