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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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2021 Student Conference
April 8–10, 2021
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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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February 2021
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DOE lists five stories to watch in 2021
Despite all the challenges of the COVID-19 pandemic, the U.S. nuclear energy community pulled out some big wins in 2020, and this year could be even bigger, according to the Department of Energy’s Office of Nuclear Energy.
From deep space exploration on Mars to a historic new reactor coming online in Waynesboro, Ga., 2021 will be a record-breaking year for the industry—both good and potentially bad.
Find the full details on the DOE-NE website.
Technical Session|Sponsored by MSTD
Tuesday, November 17, 2020|11:00AM–1:10PM (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)
Summary
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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