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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Brighton I/II
Session Chair:
Alex Levinsky
Alternate Chair:
Chang-ho Lee (ANL)
To access paper attachments, you must be logged in and registered for the meeting.
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Modeling and Analysis of a Micro-Reactor Using the DireWolf Code Suite
Nathan Roskoff (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Alex Levinsky (Westinghouse Electric Co.), Vincent Laboure (INL), Jackson Harter (INL), Adam Zabriskie (INL), Lise Charlot (INL)
Paper
Simulation of a TRISO-Fueled Heat-Pipe Microreactor Using MOOSE-Based Reactor Physics Code Griffin
Yan Cao (ANL), Nicolas Stauff (ANL), Yinbin Miao (ANL), Kun Mo (ANL), Justin Thomas (ANL), Bo Feng (ANL), Zhaopeng Zhong (ANL), Chang-ho Lee (ANL)
Preliminary Neutronic-Thermal-Mechanical Coupling of a Small Heat-Pipe Reactor Using OpenMC and MOOSE
William Reed Kendrick (MIT), Benoit Forget (MIT)
Presentation Video (Visible to Attendees)
Design, Simulation, and Analysis of a Microreactor Experiment at the National Criticality Experiments Research Center
Mikaela Blood (LANL), Alexis Maldonado (LANL), Nicholas Thompson (LANL), Holly Trellue (LANL)
Attachment — ppt
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