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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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May 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC dockets construction permit for Dow, X-energy SMR
The Nuclear Regulatory Commission has accepted Dow’s construction permit application to build an X-energy small modular reactor in Seadrift, Texas.
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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