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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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Sei-Hun Yun et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 373-378
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12383
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to obtain thermo physical properties of ZrCo and ZrCo hydride, which determine heat transfer phenomena in the hydrogen-ZrCo system. Heat capacity, thermal diffusivity and thermal conductivity of ZrCo and ZrCo hydride using Baotou ZrCo (China) are found to have U shaped curvatures with the temperature increase. In the temperature range of 300 - 500 K the thermal conductivity of ZrCoHx was found to be about 2/3 that of ZrCo and the initial hydrogen content of ZrCoHx used in this study was taken to be x=2.0.
