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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.