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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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NRC news roundup
Here’s a look at some recent announcements from the Nuclear Regulatory Commission.
Summer SLR: The NRC this month published its final environmental impact statement for Summer Unit 1’s subsequent license renewal application. Dubbed a supplemental EIS, the report is an important step in determining if Dominion Energy can continue operating its 966-MWe Westinghouse pressurized water reactor unit for an additional 20 years beyond August 6, 2042, the current end of its license.
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)
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