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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Technical Session|Sponsored by Fundamental Irradiation Damage
Thursday, December 14, 2023|3:10–4:50PM CST|Galerie 6
Session Chair:
Anne A. Campbell (ORNL)
Alternate Chair:
Flyura Djurabekova (Univ. Helsinki)
Track Organizers:
Steve Zinkle (University of Tennessee & Oak Ridge National Laboratory)
Mitra Taheri (Johns Hopkins University)
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Kinetics and Stability of Nano-Scale Precipitates in Fe-Based Alloys During Ion Irradiations
3:10–3:50PM CST
Yajie Zhao (ORNL), Pengcheng Zhu (Univ. Tennessee, Knoxville), Jonathan Poplawsky (ORNL), Arunodaya Bhattacharya (U.K. Atomic Energy Authority), Steven Zinkle (Univ. Tennessee, Knoxville)
Presented by Siwei Chen (Univ. Tennessee, Knoxville)
Paper
Impact of Micro-Alloying and Precipitation in Ion-Irradiated Nickel: From the Inhibition of Point-Defect Cluster Diffusion by Thermal Segregation to the Change of Dislocation Loop Nature
3:50–4:10PM CST
M. Loyer-Prost (CEA), K. Ma (CEA), B. Décamps (Univ. Paris-Saclay), L. Huang (CEA), M. Nastar (CEA), R.E. Schäublin (ETH Zurich), J.F. Löffler (ETH Zurich), A. Fraczkiewicz (CNRS), M.A. Belghoul (CEA), P. Vermaut (CNRS), F. Prima (CNRS)
Beryllium Carbide Tolerance to Radiation Damage for Advanced Reactor Moderators
4:10–4:30PM CST
Diego A. Muzquiz (Univ. Michigan), Stephen S. Raiman (Univ. Michigan)
Temperature Dependent Evolution of Microstructure in Fe10Cr Alloy Under Proton Irradiation
4:30–4:50PM CST
Siwei Chen (Univ. Tennessee, Knoxville), Yajie Zhao (ORNL), Yao Li (Univ. Tennessee, Knoxville), Qinyun Chen (Univ. Tennessee, Knoxville), Steven J. Zinkle (Univ. Tennessee, Knoxville)
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