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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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December 2024
Nuclear Technology
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November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Technical Session|Sponsored by NCSD
Thursday, June 11, 2020|12:15–2:00PM EDT
Session Chair:
Kristin N. Smith
Alternate Chair:
Travis M. Greene
Session Organizer:
Vladimir Sobes
Staff Producers:
Patricia Schroeder (American Nuclear Society)
Kathryn Murdoch (American Nuclear Society)
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Description and Use of SCALE Sampler Parametric Capability for Engineering Analysis and Optimization
W. J. Marshall (ORNL), T. M. Greene (ORNL), B. D. Brickner (ORNL), R. A. Hall (ORNL)
Paper
Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Applicable Experiment Selection
W. J. Marshall (ORNL), J. B. Clarity (ORNL), K. Banerjee (ORNL)
Performing keff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS: Sensitivity Calculations
Criticality Safety Analysis of Fresh Fuel Storage of Barakah Nuclear Power Plant
Shaikha A. AlShamsi (Univ. of Sharjah), Walid A. Metwally (Univ. of Sharjah), Batool M. Madani (Univ. of Sharjah)
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