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
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Seth Strege, Serkan Yilmaz, Pradip Saha, Eric P. Loewen
Nuclear Technology | Volume 193 | Number 2 | February 2016 | Pages 259-275
Technical Paper | doi.org/10.13182/NT14-120
Articles are hosted by Taylor and Francis Online.
Electromagnetic (EM) pumps are a major component in the safe operation of liquid metal–cooled nuclear reactors and can also be used in any other application in which a conductive fluid is being pumped through a system. During the design of an EM pump, it is useful to model its operating characteristics for pump sizing, flow capabilities, and other design checks. The EM pump analysis code known as MATRIX is a prime example of a tool that can be used for such pump modeling. This paper introduces the modernization and capability investigation efforts completed on MATRIX. An output data comparison of the modernized code is made between both the legacy code and the measured EM pump. Further improvement of MATRIX through data analysis and flow correction techniques is explained.