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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.
Jin Won Kim, Dae Soo Lee, Jong Hyun Kim
Nuclear Technology | Volume 134 | Number 1 | April 2001 | Pages 15-22
Technical Paper | NURETH-9 | doi.org/10.13182/NT01-A3182
Articles are hosted by Taylor and Francis Online.
In the intake structure of a nuclear power plant, undesirable pump operating characteristics such as vortices and nonuniform pump-approach flow around the pump bells take place frequently due to poorly arranged intake geometry. Therefore, prior to the construction or renovation of intake structure or internal auxiliary facilities, a hydraulic modeling test should be performed to predict the undesirable hydraulic phenomena. In this study, a three-dimensional turbulence model was applied for a numerical modeling test, and a 1:10 scale, geometrically undistorted physical model was employed to investigate the hydraulic behavior and simulate pump operating conditions in the intake structure of Kori Nuclear Units 3 and 4 in Korea. The results from these numerical and physical model tests were compared, and an antivortex device was also proposed to ensure a stable suction condition of the pumps.
