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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Jun 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
Technical Session|Sponsored by OPD
Tuesday, June 13, 2023|10:00–11:45AM EDT|Tennessee
Session Chair:
Temi Adeyeye (NuScale)
Alternate Chair:
Timothy M. Crook (Blue Wave AI Labs)
Session Organizer:
William N. Mann (ANL)
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Evaluating Scaling Effects of Steam Condensation Physics-Based Model for Small Modular Reactor
10:00–10:20AM EDT
Palash K. Bhowmik (INL), Joshua P. Schlegel (Missouri Univ. Science and Technology), Piyush Sabharwall (INL)
Paper
Accelerating Nuclear Fuels and Materials Qualification by Multi-Level Irradiation Experiment Campaign
10:20–10:40AM EDT
Palash K. Bhowmik (INL), Piyush Sabharwall (INL), Brenden Heidrich (INL), Richard H. Howard (ORNL)
Effect of Fuel-Moderator Porosity in Advanced HTGR Designs on the Depressurized Loss of Forced Convection and Compressor Power Requirements
10:40–11:00AM EDT
John Matulis (Purdue), Hitesh Bindra (Purdue)
Damage Assessment of Advanced High Temperature Fluid Reactor Piping System with Guided Wave Ultrasonics
11:00–11:20AM EDT
Chenxi Xu (Univ. Illinois, Chicago), Matthew Daly (Univ. Illinois, Chicago), Alexander Heifetz (ANL), Derek Kultgen (ANL), Didem Ozevin (Univ. Illinois, Chicago)
Transient Modelling of HTGR Thermal Load Follow in Modelica
11:20–11:40AM EDT
Aidan Rigby (Univ. Wisconsin, Madison), Ben Lindley (Univ. Wisconsin, Madison), Daniel Mikkelson (INL)
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