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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
Nuclear Technology
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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.
12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021)
Technical Session
Wednesday, June 16, 2021|12:00–1:45PM EDT
Session Chair:
Graeme M. West
Alternate Chair:
Jamie B. Coble
Session Organizer:
Staff Producer:
Ashley Jiminian (ANS)
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Automated Image Stitching of Down Channel Nuclear Reactor Fuel Channel Inspection Footage
Michael Devereux (Univ. of Strathclyde), Paul Murray (Univ. of Strathclyde), Graeme West (Univ. of Strathclyde)
Paper
Attachment — Bio
An Innovative Crack Detection Algorithm to Support Automated Inspection of Nuclear Reactor Cores
Efstathios Branikas (Univ. of Strathclyde), Paul Murray (Univ. of Strathclyde), Graeme West (Univ. of Strathclyde)
Machine Learning of Flash Thermography Images for Detection of Early Stage Fatigue in Martensitic Steel
Xin Zhang (Illinois Institute of Technology), Jafar Saniie (Illinois Institute of Technology), Thiago Seuaciuc-Osorio (Electric Power Research Institute), Sasan Bakhtiari (ANL), Alexander Heifetz (ANL)
Gaussian Process Ensemble for Corrosion Modeling and Prediction in Molten Salt Reactors
Elizabeth Sooby (Univ. of Texas San Antonio), Miltiadis Alamaniotis (Univ. of Texas at San Antonio), Alexander Heifetz (ANL)
Automated Generation of Training Dataset for Crack Detection in Nuclear Power Plant Components
Zhouxiang Fei (Univ. of Strathclyde), Graeme M. West (Univ. of Strathclyde), Paul Murray (Univ. of Strathclyde), Gordon Dobie (Univ. of Strathclyde)
Attachment — Updated version of the paper
Attachment — Biography
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