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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Woan Hwang, Cheol Nam, Thak Sang Byun, Young Cheol Kim
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 130-141
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2887
Articles are hosted by Taylor and Francis Online.
Computational models for analyzing in-reactor behavior of metallic fuel pins in liquid-metal reactors under steady-state conditions are developed and implemented in the Metal fuel performance Analysis (computer) Code for Simulating the In-reactor behavior under Steady-state conditions (MACSIS). Sodium logging and constituent redistribution effects are considered in calculating the temperature profile. The model for the radial redistribution of the fuel constituent is based on the thermotransport theory. The fission gas release model takes multibubble size distribution into account to characterize the lenticular bubble shape and the saturation condition on the grain boundary. Finally, the clad strains are calculated from the amount of fission gas released and interface pressure. Sample calculations are performed to verify each model. The results show that in general, the predictions of MACSIS agree well with the available irradiation data.
