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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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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.
Blair P. Bromley
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 546-560
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-851
Articles are hosted by Taylor and Francis Online.
A study of computational/analytical neutronics and heat transfer has been carried out for different types of gas-cooled fuel bundle lattices that could be used for the sub-critical fertile/fissionable blanket of a cylindrical-geometry hybrid fusion-fission reactor (HFFR) with thorium-based fuels. The HFFR concept envisioned is one with a simple cylindrical geometry, using an anticipated variant of a magnetic mirror to confine a deuterium-tritium (DT) fusion plasma. The annular-cylindrical blanket is approximately 10 meters long and 2 meters thick, and is a repeating lattice of pressure tubes filled with 0.5-meter fuel bundles that are made of (233U,Th)O2, and refuelled continuously on-line, sharing technological features with pressure-tube heavy water reactors (PT-HWR) and the Advanced Gas-Cooled Reactor (AGR) in the U.K.. With a 2-meter thick blanket, the average fissile content in the blanket needs to be at least 2.5 wt% in order for the HFFR system to be self-sustaining in power.
