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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Yine-Ping Ting
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 94-103
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33667
Articles are hosted by Taylor and Francis Online.
The RETRAN analysis of San Onofre Nuclear Generating Station Unit 2 (SONGS 2) turbine trip from 100% power is a continuing effort of our in-house RETRAN model development to benchmark the calculations against the plant test data. The previous benchmarked calculations—RETRAN analyses of SONGS 2 flow measurements and low-power natural circulation test—showed very good agreement with the plant test data. The latter RETRAN model was then expanded for the current study to include steam generator secondary side, main steam line pipings, control valves, and plant control systems. The benchmarked turbine trip model has been used to analyze the station-requested plant operational transients. These are (a) assessment of strategies for performing turbine overspeed surveillance, (b) determining a manual position of one steam bypass valve following a reactor trip from 100% power, and (c) plant response to one main steam isolation valve closure at 90 and 50% power levels. In addition, the RETRAN calculations employing benchmarked models can be used to verify the simulator predictions and assess the existing plant operating procedures.