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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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Apr 2025
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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.
International Conference on Physics of Reactors 2024
Dr. Per Peterson is a Co-Founder & Chief Nuclear Officer of Kairos Power. Dr. Peterson also holds the William and Jean McCallum Floyd Chair in the Department of Nuclear Engineering at the University of California, Berkeley.
He is an expert in topics related to high-temperature fission energy systems, safety and security of nuclear materials, and waste management. As a member of the Evaluation Methodology Group, he participated in the development of the Gen IV Roadmap while serving as co-chair for the Proliferation Resistance and Physical Protection Working Group. His research has contributed to the development of the passive safety systems used in the General Electric ESBWR and Westinghouse AP1000 reactor designs. With Charles Forsberg and Paul Pickard, in 2003, he proposed the FHR concept of a molten-salt cooled, solid fueled reactor.
Dr. Peterson graduated from the University of Nevada at Reno with a B.S. in Mechanical Engineering. He holds an M.S. and Ph.D. in Mechanical Engineering from the University of California, Berkeley.
Last modified February 15, 2024, 1:19pm PST
