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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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“Life is a roller coaster. It’s best ridden with your hands in the air.”
Craig Piercycpiercy@ans.org
I find myself saying the expression above a lot these days—to my kids, my wife, my friends, and colleagues. Most recently, I said it to the person sitting next to me after the pilot of our plane—bound for Reagan National Airport a day after the collision of AA flight 5342 and a military Blackhawk helicopter—aborted the landing at the last minute.
I am not sure where I picked up this pronouncement, but I find it to be apropos to the topsy-turvy moment where we find ourselves in 2025. In addition to the first U.S. commercial airline crash in 15 years, we are witnessing a new presidential administration in its infancy playing by the Silicon Valley rules of “move fast, break things.” We’ve seen DeepSeek, the low-cost Chinese AI that reportedly uses 50–75 percent less energy than its NVIDIA-powered counterparts, tank Constellation’s market value by more than 20 percent in one late-January trading day.
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)
To access the session recording, you must be logged in and registered for the meeting.
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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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