ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
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.