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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.
B. K. Kamboj, S. M. Ghiaasiaan, and, S. I. Abdel-Khalik
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 347-360
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34730
Articles are hosted by Taylor and Francis Online.
A phenomenological model is developed for the thermal-hydraulic processes on the secondary side of a once-through steam generator during auxiliary feedwater injection. Based on experimental observations, the flow of auxiliary feedwater in the secondary side is modeled as a turbulent falling film on the tubes, in direct contact with a countercurrent flow of steam, that receives heat from the primary side. Conservation equations for the falling film and steam on the secondary side, and for the primary-side coolant, are derived. Boiling in the falling film, evaporation and/or condensation at the falling film-gas interphase, and countercurrent flow limitation in the tube support plate passages are modeled. Numerical solution of the conservation equations provide the axial variation of flow rates and temperatures in the primary and secondary sides. Model predictions are successfully compared with the available experimental data.