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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.
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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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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.
A. Mayoral, J. Sanz, D. López, R. Vila
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 276-282
Fusion Technology Facilities | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14147
Articles are hosted by Taylor and Francis Online.
The Spanish Technofusion project includes an irradiation laboratory equipped with two tandem-type accelerators (protons/deuterons and alphas) and a multi-ion cyclotron (heavy ions).A radioprotection issue concerning activation of the irradiated samples is to establish the required "cooling" waiting period for safe handling. Samples of iron, Al2O3, SiO2, and SiC are considered here.In dealing with this task, inventory calculations have been performed using, in addition to cross-section data available in different activation libraries, experimental data for some dominant reactions that have not yet been considered in the generation of the corresponding evaluated activation cross sections. Residual dose rate results, calculated from the radioactive inventory determined using both evaluated data alone and a combination of evaluated and experimental data, are compared and the impact of the results on handling limitations analyzed.Very affordable cooling times are found suitable for the irradiated samples. The calculated cooling times meeting safe handling requirements are expected to have high reliability for the proton beam in Al2O3 and the alpha beam in Fe and relatively high reliability for the proton beam in SiO2 and Fe as well as the alpha beam in Al2O3 and SiO2; only deuteron beam is satisfactory for Al2O3; and finally, for SiC, all cases are unsatisfactory.
