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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nov 2024
Jul 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Technical Session|Sponsored by Evolution of Material Properties
Monday, December 11, 2023|9:30–11:30AM CST|Galerie 1
Session Chair:
Gary Was (Univ. Michigan)
Track Organizers:
Thak Sang Byun (ORNL)
Dong Liu (University of Bristol)
Alternate Chair:
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A Review of the Mechanical Properties of the 316 Stainless Steel Family for Advanced Nuclear Reactors Application
9:30–9:50AM CST
R. Song (INL), M.D. Eklund (INL), A.M Jokisaari (INL), R.A. Roach (INL), C. Topbasi (EPRI)
Paper
Influence of Initial Microstructure and Sampling Location on the Mechanical Behavior of Additively Manufactured 316L Stainless Steel After Neutron Irradiation
9:50–10:10AM CST
Thak Sang Byun (ORNL), Jesse W. Werden (ORNL), Maxim N. Gussev (ORNL), Timothy G. Lach (ORNL), Annabelle Le Coq (ORNL), Kory Linton (ORNL)
Applying Micro-Tensile Testing, Atom Probe Tomography, and High-Resolution TEM Characterization to Harvested High Dose Zorita Light Water Reactor Internals
10:10–10:30AM CST
Cameron Howard (INL), Mukesh Bachhav (INL), Boopathy Kombaiah (INL), Fei Teng (INL), Sohail Shah (INL), Yachun Wang (INL), Jason Daniel (U.S. Nuclear Regulatory Commission)
Analysis of Porosity Defects and Their Impact on Tensile Behavior in LPBF Stainless Steel 316 L Utilizing X-ray Computed Tomography
10:30–10:50AM CST
Tasrif UI Anwar (Utah State), Patrick Merighe (Utah State), Rahul Reddy Kancharla (INL), Boopathy Kombaiah (INL), Nadia Kouraytem (Utah State)
In-Situ 3D High-Energy X-ray Diffraction Study on Deformation Behavior of Neutron-Irradiated Fe-9%Cr
10:50–11:10AM CST
Dominic Piedmont (Univ. Illinois, Urbana-Champaign), Jun-Sang Park (ANL), Peter Kenesei (ANL), Jonathan Almer (ANL), Matthew Kasemer (Univ. Alabama), Ezra Mengiste (Univ. Alabama), Meimei Li (ANL), Xuan Zhang (ANL), James F. Stubbins (Univ. Illinois, Urbana-Champaign)
Atomistic Simulation of Hydrogen Segregation to Grain Boundaries and Crack Tips
11:10–11:30AM CST
Richard W. Smith (Naval Nuclear Laboratory)
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