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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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 News 40 Under 40: The wait is over
Following the enthusiastic response from the nuclear community in 2024 for the inaugural NN 40 Under 40, the Nuclear News team knew we had to take up the difficult task in 2025 of turning it into an annual event—though there was plenty of uncertainty as to how the community would receive a second iteration this year. That uncertainty was unfounded, clearly, as the tight-knit nuclear community embraced the chance to celebrate its up-and-coming generation of scientists, engineers, and policy makers who are working to grow the influence of this oft-misunderstood technology.
M. A. Hassan, K. Rehme
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 401-414
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32714
Articles are hosted by Taylor and Francis Online.
The influence of spacer grids on the heat transfer in gas-cooled rod bundles was determined experimentally for the first time over a wide range of parameters. The experimental investigations were carried out with a smooth and a rough rod bundle for Reynolds numbers between 600 and 2 × 105. The measured range of Reynolds numbers covered the transition from laminar to turbulent, the transition from hydraulically smooth to rough, and fully rough flows. In gas cooling, artificial roughnesses on the rod surfaces are used to disturb the viscous sublayer, which acts as an insulator because of the low thermal conductivity of gases. For this investigation, a two-dimensional rectangular roughness was used, which had an optimum heat transfer characteristic. The blockage factor ∊ was varied between 25 and 35%. These values are typical of flow blockages due to spacer grids in gas-cooled fast reactors. The measurements were carried out from 10 Dh upstream to 33 Dh downstream of the spacer grid. The measured range covered the zone of heat transfer influenced by the spacer grid. The measurements showed heat transfer to be improved by spacer grids in all cases investigated. On the basis of the measurements, empirical correlations could be established for the influence of the spacer grid on heat transfer in terms of the measured parameters, i.e., Reynolds number, blockage factor, and the type of heat transfer surface. These empirical correlations can be directly used in computer codes for analysis of the thermodynamics and fluid dynamics of gas-cooled rod bundles.