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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
Technical Session|Sponsored by MSTD
Tuesday, November 17, 2020|12:00–2:10PM EST
Session Chair:
Cynthia A. Adkins
Alternate Chair:
Colby B. Jensen
Session Organizer:
Kenneth J. Geelhood
Staff Producer:
Jessie Vazquez (American Nuclear Society)
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High Temperature Deformation Processes in Additively Manufactured 316L Stainless Steel
Meimei Li (Argonne National Laboratory), Kurt Terrani (ORNL), T.S. Byun (ORNL), Florent Heidet (ANL), Wei-Ying Chen (ANL), Xuan Zhang (ANL)
Paper
Deformation and Fracture Characteristics of Additively Manufactured and Wrought 316L Stainless Steels before and after Irradiation
Kurt A. Terrani (Oak Ridge National Laboratory), Timothy G. Lach (Oak Ridge National Laboratory), Joseph J. Simpson (Oak Ridge National Laboratory), Benton Garrison (ORNL), Maxim Gussev (Oak Ridge National Laboratory), Thak Sang Byun (Oak Ridge National Laboratory)
Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory
Gokul Vasudevamurthy (Oak Ridge National Laboratory)
Chemistry Effects on α' precipitation in FeCrAl Alloys
Russell M. Fawcett (Global Nuclear Fuel), Dan Lutz (Global Nuclear Fuel - Americas), Soumya Nag (GE Research), Raul B. Rebak (GE Research), Andrew K. Hoffman (GE Global Research Center)
EFFECT OF HYDRIDE ON CRACK GROWTH IN ZIRCONIUM ALLOY BY EXTENDED FINITE ELEMENT SIMULATION
Huaping Dong (Science and Technology on Reactor System Design Technology Laboratory), Meng Huo (Science and Technology on Reactor System Design Technology Laboratory), Ximing Xie (Science and Technology on Reactor System Design Technology Laboratory), Lili Liu (Science and Technology on Reactor System Design Technology Laboratory), Hua Pang (Science and Technology on Reactor System Design Technology Laboratory), Xiaoming Song (Science and Technology on Reactor System Design Technology Laboratory), Liang Chen (Nuclear Power Institute of China)
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