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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.
Andrea Rizzolo, Piero Agostinetti, Mauro Breda, Moreno Maniero, Diego Marcuzzi, Modesto Moressa, Matteo Valente
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 164-170
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14130
Articles are hosted by Taylor and Francis Online.
The ITER Neutral Beam Test Facility (PRIMA - Padova Research on ITER Megavolt Accelerator) is planned to be built at Consorzio RFX (Padova, Italy). PRIMA includes two experimental devices: a full-size plasma source with low voltage extraction called SPIDER (Source for Production of Ions of Deuterium Extracted from RF plasma) and a full-size neutral beam injector at full beam power called MITICA (Megavolt ITER Injector Concept Advancement).The beam source components are exposed to high and focused heat loads during beam production, and they are actively cooled, being at high voltage, by ultrapure water, which flows through cooling channels machined inside the components. The high power loads, the complexity of the cooling circuits, and their small, rectangular cross sections are design critical issues.The results of the tests carried out on the single cooling channel prototypes (SCPs) for the SPIDER accelerator grids and their performances in terms of pressure drop and heat exchange calculation are presented. The SCPs have been tested in environmental conditions similar to injector ones, i.e., they have been subjected to thermal loads up to the average heat power density of 1 MW/m2 , in a vacuum environment (0.5 Pa). The experimental results have been cross-checked with computational fluid dynamics analyses and analytical models.
