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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
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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