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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
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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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Dragonfly, a Pu-fueled drone heading to Titan, gets key NASA approval
Curiosity landed on Mars sporting a radioisotope thermoelectric generator (RTG) in 2012, and a second NASA rover, Perseverance, landed in 2021. Both are still rolling across the red planet in the name of science. Another exploratory craft with a similar plutonium-238–fueled RTG but a very different mission—to fly between multiple test sites on Titan, Saturn’s largest moon—recently got one step closer to deployment.
On April 25, NASA and the Johns Hopkins University Applied Physics Laboratory (APL) announced that the Dragonfly mission to Saturn’s icy moon passed its critical design review. “Passing this mission milestone means that Dragonfly’s mission design, fabrication, integration, and test plans are all approved, and the mission can now turn its attention to the construction of the spacecraft itself,” according to NASA.
Kwang-Yong Kim, Jun-Woo Seo
Nuclear Technology | Volume 149 | Number 1 | January 2005 | Pages 62-70
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT05-A3579
Articles are hosted by Taylor and Francis Online.
In the present work, the shape of a mixing vane in a pressurized water reactor fuel assembly has been optimized numerically using three-dimensional Reynolds-averaged Navier-Stokes analysis of the flow and heat transfer to find the effects of flow characteristics downstream of the mixing vane on heat transfer augmentation and also to optimize the shape of the mixing vane to increase the resistance to departure from nucleate boiling by enhancing the heat transfer without excessive pressure loss. The response surface method is employed as an optimization technique. The objective function is defined as a combination of the heat transfer rate and the inverse of friction loss with weighting factor. The bend angle and base length of the mixing vane are selected as design variables. In most of the numerical experiments, both the heat transfer and friction loss are enhanced as the bend angle and base length increase. The swirl and cross-flow characteristics and thermal-hydraulic performances of different shapes of mixing vane are discussed. From the results, the close relationship between the swirl factor and the heat transfer rate has been found. In the specified ranges of the design variables, the sensitivity of the objective function to the base length is only about one-tenth of the sensitivity to the bend angle. Nine points for numerical experiments were sufficient for construction of a reliable response surface. The optimum shape has been obtained as a function of the weighting factor in the objective function.