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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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DOE issues new NEPA rule and procedures—and accelerates DOME reactor testing
Meeting a deadline set in President Trump’s May 23 executive order “Reforming Nuclear Reactor Testing at the Department of Energy,” the DOE on June 30 updated information on its National Environmental Policy Act (NEPA) rulemaking and implementation procedures and published on its website an interim final rule that rescinds existing regulations alongside new implementing procedures.
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Technology | Volume 210 | Number 11 | November 2024 | Pages 2050-2073
Research Article | doi.org/10.1080/00295450.2024.2309080
Articles are hosted by Taylor and Francis Online.
The utilization of a grid spacer with vane is a significant component within reactor fuel channels. The presence of the vane has a notable impact on the mixing of flow and the enhancement of heat transfer within subchannels. The purpose of this work was to perform a numerical analysis of the effects of the vane deflection angle on the flow-thermal characteristics in a fuel rod assembly.
In the current analysis, a square array consisting of a 5 × 5 rod bundle was utilized. The pitch-to-rod diameter ratio was set to 1.33, while the blockage ratio of the grid spacer was determined to be 0.16. A relative study was made for flow-thermal characteristics with four different vane deflection angles, such as 21 deg, 25 deg, 29 deg, and 33 deg. Analyses were made for a fluid pressure of 15.5 MPa, an inlet temperature of 583 K, and a velocity of 4.74 m/s.
The present study investigated the Shear Stress Transport (SST) k-ω and Renormalization Group (RNG) k-ε turbulence models to analyze flow phenomena and thermal performance. The numerical results were validated through experimental data and also compared with correlations proposed by researchers. The analysis of the results was carried out using various methods, including the examination of data curves and streamlines, as well as vector and contour plots. The results indicate that a higher deflection angle leads to a greater reduction in temperature at the grid spacer. The swirl ratio was observed to be maximum close downstream to the grid spacer, and the persistence of the swirl ratio in the downstream can enhance the performance of departure of nucleate boiling. The vane on the grid spacer with a higher deflection angle enhances the coefficient of heat transfer remarkably close to the downstream grid spacer.