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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Nadish Saini, Shrey Satpathy, Igor A. Bolotnov (NCSU)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 635-641
In the dispersed flow film boiling regime the dominant path of heat transfer from the fuel rods is to the entrained droplets in the reactor sub-channels. The heat transfer coefficient strongly correlates to the surface area of the droplets, which is effectively characterized by the Sauter mean diameter. Owing to the interaction of droplets with spacer grids and mixing vanes sharp increase in heat transfer coefficients are reported immediately downstream of spacer grids by prior experiments.
In this study, using state of the art computing facilities and the massively parallel PHASTA code, we present high resolution simulations of droplet-spacer grid interactions under conditions similar to DFFB flow regime. Level-set based interface tracking method is used to resolve the interface between the two phases. Fully developed turbulent flow field is obtained from single-phase steam flow adiabatic simulations. Two-phase simulations are performed by superimposing the level set contour over the obtained single phase velocity field. The results from twophase simulations demonstrate the capability of PHASTA code to capture the interface during droplet spacer-grid collision events.
The objective of the present work is to collect numerical data on the Sauter mean diameter of droplets downstream of spacer grids. The data will be compared with the experiments and existing mechanistic correlations in the literature for Sauter mean diameter modification due to spacer grids. The results from the simulations will serve to improve the correlations in thermal hydraulic codes and can also serve as training data for reduced order twophase flow modeling.