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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Zaporizhzhia ‘extremely fragile’ relying on single off-site power line, IAEA warns
Europe’s largest nuclear power plant has just one remaining power line for essential nuclear safety and security functions, compared with its original 10 functional lines before the military conflict with Russia, warned Rafael Mariano Grossi, director general of the International Atomic Energy Agency.
X. Cheng, N. I. Tak
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 229-236
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT158-229
Articles are hosted by Taylor and Francis Online.
Computational fluid dynamics (CFD) analysis is carried out for heat transfer of lead-bismuth eutectic flows in rod bundles. The effect of different parameters, such as turbulence models, on the numerical results is investigated. The effect of meshes on the heat transfer is much smaller when using the [curly epsilon]-type turbulence models than when using the -type turbulence models. Based on the results achieved, the Reynolds stress model of Speziale with fine-mesh structures, i.e., y1+ 15, is recommended for further CFD analysis of heavy liquid-metal (HLM) flows in rod bundles. A strong circumferential nonuniformity of heat transfer is observed in tight rod bundles, especially in square lattices. The secondary flow leads to a reduction in the nonuniformity of heat transfer. Related to the overall average Nusselt number, CFD codes give similar results for both triangular and square rod bundles when the Peclet number and the pitch-to-diameter ratio have the same values in both bundle configurations. Comparison of the CFD results with bundle test data in mercury clearly indicates that the turbulent Prandtl number for HLM flows in rod bundles is smaller than that in circular tubes. It has values close to 1.0 at high Peclet number conditions and increases by decreasing Peclet number.