Papers

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High Temperature Deformation Processes in Additively Manufactured 316L Stainless Steel

Meimei Li (Argonne National Laboratory), Xuan Zhang (ANL), Wei-Ying Chen (ANL), Florent Heidet (ANL), T.S. Byun (ORNL), Kurt Terrani (ORNL)

Deformation and Fracture Characteristics of Additively Manufactured and Wrought 316L Stainless Steels before and after Irradiation

Thak Sang Byun (Oak Ridge National Laboratory), Maxim Gussev (Oak Ridge National Laboratory), Benton Garrison (ORNL), Joseph J. Simpson (Oak Ridge National Laboratory), Timothy G. Lach (Oak Ridge National Laboratory), Kurt A. Terrani (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

Andrew K. Hoffman (GE Global Research Center), Raul B. Rebak (GE Research), Soumya Nag (GE Research), Dan Lutz (Global Nuclear Fuel - Americas), Russell M. Fawcett (Global Nuclear Fuel)

EFFECT OF HYDRIDE ON CRACK GROWTH IN ZIRCONIUM ALLOY BY EXTENDED FINITE ELEMENT SIMULATION

Liang Chen (Nuclear Power Institute of China), Xiaoming Song (Science and Technology on Reactor System Design Technology Laboratory), Hua Pang (Science and Technology on Reactor System Design Technology Laboratory), Lili Liu (Science and Technology on Reactor System Design Technology Laboratory), Ximing Xie (Science and Technology on Reactor System Design Technology Laboratory), Meng Huo (Science and Technology on Reactor System Design Technology Laboratory), Huaping Dong (Science and Technology on Reactor System Design Technology Laboratory)


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