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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Argonne opens registration for D&D training course
Registration is open for Argonne National Laboratory’s Facility Decommissioning Training Course, a four-day instruction designed for those responsible for the decontamination and decommissioning of nuclear facilities and who are looking to understand the full breadth and depth of the D&D processes.
The next session will be held July 16–19 in Santa Fe, N.M. Information on the course and how to register can be found here.
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.