ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
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.
Yassin A. Hassan*
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 176-188
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33802
Articles are hosted by Taylor and Francis Online.
Simulations of FLECHT and FLECHT-SEASET, unblocked forced flow reflood tests, were performed using RELAP5/MOD2 code reflood capabilities. The predictions of the high flooding injection rate and steam cooling tests were in good agreement with the measurements. The low flooding rate tests showed a tendency to predict lower peak cladding temperatures than the data and unrealistic void fraction oscillations. The spikes in void fraction histories were flow-regime dependent. The prediction for the quench times at the upper bundle elevations was overestimated.
