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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
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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