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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
Steam is a sign of cooling system function . . . at ITER
Steam from one of ITER’s ten induced-draft cooling cells offers visual confirmation of a successful cooling system test, the ITER organization announced April 30. ITER’s cooling system features 60 kilometers of piping with pumps, filters, and heat exchangers that can pull water through at up to 14 cubic meters per second. Once fully operational, two cooling loops—one to remove the heat generated by the plasma in the ITER tokamak and one for its supporting infrastructure—will be capable of extracting up to 1,200 MW of heat.
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.