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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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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.
Gayeon Ha, Sanghwa Lee, Gyunyoung Heo (Kyung Hee Univ), Hana Seo, Yujeong Choi (Korea Inst of Nuclear Nonproliferation and Control)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1260-1266
Nuclear forensics is one of the activities to classify the sources of unidentified nuclear materials. Korea Institute of Nuclear Nonproliferation and Control (KINAC) has been conducting researches on this field continuously and the data-driven approaches have been studied as a forensic method for fresh and spent nuclear fuels in recent years. Under this circumstance, this article summarizes the methodologies implemented at KINAC and Kyung Hee University. It includes (1) study on identifiable signatures, (2) development of nuclear forensic library, and (3) research on classification algorithm for the identifiable signatures. There are various characteristics such as physical, chemical, and radiological properties, which are considered as the identifiable signatures of nuclear fuels. First, the fresh or spent fuel can be classified according to their radiation level. The impurities can be considered as the main signature for fresh fuels in case that they have generally a similar level of enrichment. The overall characteristics of multi-dimensional impurity dataset are extracted through Principal Component Analysis (PCA) and finally one-class Support Vector Machine (SVM) is used to classify the reactor types in which the fuel was used. In spent fuel forensics, the radionuclide mass through radiation analysis is focused on as a signature. The application of the classification of the reactor type using SVM and the regression analysis to predict the operational history, such as enrichment, burn up, and cooling time are investigated. The potential of data-drive methodologies for nuclear forensic is discussed.