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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
Fusion Science and Technology
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.
Hongli Chen, Tao Zhou, Zi Meng, Yican Wu, FDS Team
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 157-163
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14129
Articles are hosted by Taylor and Francis Online.
A Chinese dual-functional lithium lead test blanket module was proposed for testing in ITER. The flow channel insert (FCI) was inserted in LiPb flow channels to reduce magnetohydrodynamic (MHD) effects and to increase the outlet temperature of coolant LiPb. The FCI has a big influence on the LiPb flow characteristics under the high magnetic field. In this paper, the LiPb MHD flow characteristics both in the gap between the FCI and the channel wall and inside the FCI was numerically calculated using an MHD code named MTC-H 2.0 in a poloidal channel. The influence of the FCI on flow distribution was analyzed. The pressure drop was compared to the case without the FCI, and the pressure equalization was assessed for both sides of the FCI with pressure equalization openings. The impact of electrical conductivity of the FCI material was analyzed.
