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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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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.
Jun-Yi Zhang, Xiao Yan (CNNC Key Laboratory on Reactor Thermal Hydraulics Technology), Ze-Jun Xiao (Hualong Pressurized Water Reactor Technology Corporation, Ltd.), Yong-Ze Xu (CD-adapco)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1134-1143
Subcooled boiling heat transfer, which is related to Departure of Nucleate Boiling(DNB), is highly concerned in fuel assembly of PWR. It is of importance and significance to predict void fraction and mass/energy transfer characteristics among sub-channels under subcooled boiling with 3-D CFD code to obtain more details for better understanding of two-phase flow process in rod bundle. To better understand and predict void distribution and its transportation characteristics in rod bundle, two-phase flow simulation with two-fluid model was carried out with Heat Partitioning Model. In this study, the 5×5 full length PSBT rod bundle with Uniform-Axial Power Distribution (U-APD) was used under prototype condition (test serial of B5 configuration) to test the physical method. The parameter distribution in axial and radial orientation among different sub-channels at the downstream of the last Mixing Vane Grid(MVG), where the DNB occurs at the end of the heated section, was studied. Different void fraction distribution was observed among central channels, side channels and corner channels. It is induced by different mass transfer process results from the layout of mixing vanes. Moreover, different mass transfer characteristics occurred between corner channels at the different location. Energy transfer is related to the mass transfer among sub-channels. The simple support grid (SSG) shows a suppression of radial transverse flow which is introduced by the mixing vanes for heat transfer enhancement.