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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Milos I. Atz, Massimiliano Fratoni
Nuclear Technology | Volume 209 | Number 5 | May 2023 | Pages 677-695
Technical Paper | doi.org/10.1080/00295450.2022.2146475
Articles are hosted by Taylor and Francis Online.
Future utilization of nuclear power may involve fuel cycles that incorporate new reactors and new fuel utilization schemes. In comparing fuel cycles in terms of their waste characteristics, many previous studies have focused on properties intrinsic to the wastes themselves: mass, radioactivity, and/or radiotoxicity. These properties do not directly inform analyses that evaluate waste management strategies, impacts, or risks. For these, information about waste packages and waste loading is critical. This paper reports on research performed to bridge the divide between nuclear fuel cycle and waste management analyses while accommodating the diversity of reactors, processes, and waste forms that could be utilized by advanced fuel cycles. An object-oriented Python code, Nuclear Waste Analysis in Python, was written to connect fuel cycle data with backend process information, thereby generating waste form characteristics and package inventories. The backend process models are informed by literature review and engineering judgment. The package is applied to the fuel cycles considered in the Fuel Cycle Evaluation and Screening (FCES) study and is benchmarked against the FCES study waste management evaluation metric data for mass and radioactivity. Hypothetical waste package inventories are reported for each fuel cycle as functions of spent fuel and high-level waste loading.