ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
Cleanup work progresses with pump removal at Hanford Tank Farms
The Department of Energy’s Office of Environmental Management reports that workers at the Hanford Site, near Richland, Wash., have performed a technically complex operation to remove a large legacy mixer pump from Tank SY-101 in the 200 West Area. The removal allows for the future installation of tank waste retrieval equipment as part of the next phase of waste cleanup at the site.
A short video on the Hanford Site’s YouTube channel shows aspects of the operation, including the pump being lifted out of the tank with a specially designed hydraulic lift system named Hercules.
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.
Register NowLog In
To access paper attachments, you must be logged in and registered for the meeting.
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)
