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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Hongli Chen, Tao Zhou, Zi Meng, Yican Wu, FDS Team
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 157-163
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14129
Articles are hosted by Taylor and Francis Online.
A Chinese dual-functional lithium lead test blanket module was proposed for testing in ITER. The flow channel insert (FCI) was inserted in LiPb flow channels to reduce magnetohydrodynamic (MHD) effects and to increase the outlet temperature of coolant LiPb. The FCI has a big influence on the LiPb flow characteristics under the high magnetic field. In this paper, the LiPb MHD flow characteristics both in the gap between the FCI and the channel wall and inside the FCI was numerically calculated using an MHD code named MTC-H 2.0 in a poloidal channel. The influence of the FCI on flow distribution was analyzed. The pressure drop was compared to the case without the FCI, and the pressure equalization was assessed for both sides of the FCI with pressure equalization openings. The impact of electrical conductivity of the FCI material was analyzed.
