ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Jong-Hark Park, Hee-Taek Chae, Cheol Park, Heonil Kim
Nuclear Technology | Volume 160 | Number 3 | December 2007 | Pages 346-351
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT07-A3905
Articles are hosted by Taylor and Francis Online.
A tubular-type fuel assembly has been considered as one of the candidates for the fuel of the Advanced HANARO Reactor (AHR). The hydraulic characteristics of the tubular fuel under consideration have been investigated by an experiment and a computational fluid dynamics (CFD) analysis. To measure the flow distribution and the pressure drop, a test facility was constructed, and a mock-up of a tubular fuel was fabricated. A pitot tube was employed to measure the coolant velocity in the flow channels. Numerical analysis by the CFD code was also conducted to compare its results with the test results and to obtain insight into the flow structure in a tubular fuel. The simulation results by the CFD analysis showed reasonable agreement with the measurements for the flow distribution as well as good agreement for the pressure drop in a tubular fuel.