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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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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.
Xia Bing, Jiong Guo, Chunlin Wei, Ding She, Jian Zhang, Fu Li (Tsinghua Univ)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 848-852
The pebble bed high temperature reactors (PB-HTRs) are one of the promising reactor types for the next generation nuclear systems. Some intrinsic features of the PB-HTRs’ spherical fuel element embedded with the TRISO coated fuel particles bring high proliferation-resistance to the PB-HTR spent fuel storage, including the continuous on-line fueling strategy, the difficulty of processing TRISO particles, the low heavy metal density in the fuel pebbles and the high depletion of plutonium. The material accountancy concept and methodology of PB-HTR spent fuel storage are proposed in this work. For PB-HTRs, the spent fuel storage should be treated as an item facility; however, the items in PB-HTR spent fuel storage are the spent fuel containers, instead of the spent fuel assemblies in conventional PWR’s spent fuel storage. The accountancy of nuclear material should be implemented by evaluating the average burnup value of a batch of spent fuels. For the equilibrium core of PB-HTR, the average burnup value of a batch of spent fuel pebbles is determined by the integral power during the period when these pebbles are unloaded from the reactor core. Furthermore, the burnup value of each spent fuel pebble can also be measured by gamma spectroscopy upon the long-lived fission product 137Cs. After evaluating the spent fuel burnup, the dependency of the amounts of heavy metal nuclides upon the burnup value of a spent fuel pebble is estimated by the depletion calculations. It is revealed that the non-proliferation features of PB-HTR spent fuel storage is excellent and the accountancy methodology proposed in this work is feasible. Besides the high safety features, the high proliferation-resistance can be another attraction of the PB-HTRs.