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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
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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