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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
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.
Technical Session|Thermal Hydraulics
Friday, April 5, 2024|3:15–3:45PM EDT|Reber Room 135
Session Chair:
David Reger
Alternate Chair:
John J. Acierno
Session Organizer:
Carolina da Silva Bourdot Dutra (Penn State)
Dr. Joshua Hansel (INL) will present on Sockeye, a heat pipe analysis application based on the Multiphysics Object-Oriented Simulation Environment (MOOSE) finite element framework, specifically designed for modeling heat pipes in heat-pipe-cooled nuclear microreactors. This talk will cover Sockeye's transient heat pipe modeling capabilities, validation using data from the Michigan Single Sodium Heat Pipe (MISOH1) facility, and the importance of higher fidelity heat pipe models and accurate knowledge of internal dimensions for producing realistic transient behavior. Dr. Hansel will emphasize Sockeye's role in advancing the understanding and design of heat-pipe-cooled nuclear microreactors and discuss future development plans. *This presentation will be 30 minutes instead of 20 minutes.*
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A Sockeye Model of a Test at the Michigan Single Sodium Heat Pipe Facility
3:15–3:45PM EDT
Joshua E. Hansel (INL), Carolina da Silva B. Dutra (Penn State), Pei-Hsun Huang (Univ. Michigan), Taehwan Ahn (Univ. Michigan), Victor Petrov (Univ. Michigan)
Paper
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