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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
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Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Jorge V. Carvajal, Shawn C. Stafford, Jeffrey L. Arndt, Paul M. Sirianni, Melissa M. Heagy, Emre Tatli (Westinghouse), David M. Carpenter, Yakov Ostrovsky (MIT)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1000-1012
The development and commercial introduction of advanced nuclear reactor fuel is slowed by the long turnaround time required by the methodology’s cycle of in-core irradiation, cooling, shipping and post irradiation examination (PIE). PIE is complicated and costly due to the high activation of the irradiated fuel. During the development process, which can extend over several years, access to fuel cladding operating data is very limited. Incorporating a real-time, remote, fuel monitoring system into the fuel rod can provide critical information on such parameters as centerline fuel temperature, axial fuel pellet elongation and rod internal pressure that can enable fuel models to be adjusted in real time and accelerate the licensing approval process. By transmitting the information from the integral sensor through the cladding, penetrations into the fuel rod are avoided and the performance of the fuel is not compromised. Data on fuel performance is generated immediately on startup of the instrumented fuel rod and can continue throughout the life of the rod. This data can be used immediately to inform further fuel development activities and can also be used to target PIE activities to enhance their usefulness and reduce costs. This paper will describe the prototype sensor development, operation and results obtained during the irradiation program at the Massachusetts Institute of Technology Reactor (MITR).