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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
Fusion energy radwaste management considerations
The question of what to do with the radioactive waste has been raised frequently for both fission and fusion. In the 1970s, fusion adopted the land-based disposal option, primarily based on the Nuclear Regulatory Commission’s decision to regulate all radioactive wastes as only a disposal issue, following the fission guidelines. In the early 2000s, members of the Advanced Research Innovation and Evaluation Study (ARIES) national team became increasingly aware of the high amount of mildly radioactive materials that 1-GWe fusion power plants will generate, compared with the current line of fission reactors. The main concern is that such a sizable inventory of mostly tritiated radioactive materials would tend to rapidly fill U.S. repositories—a serious issue that was overlooked in early fusion studies1 that could influence the public acceptability of fusion energy and will certainly become more significant in the immediate future if left unaddressed, as fusion moves toward commercialization.
Technology of Fusion Energy (TOFE)
Thursday, June 16, 2022|3:15–5:00PM PDT|Huntington B/C
Jason Trelewicz (Stony Brook Univ.)
Lauren M. Garrison (ORNL)
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Nuclear Data Experiments for Fusion: Challenges, Successes, and Future Needs
Mark Gilbert (United Kingdom Atomic Energy Authority)
Small Specimen Test Technique Development for Materials Qualification Using Fusion Neutron Source
Xiang Chen (ORNL), Mikhail A. Sokolov (ORNL), Takashi Nozawa (National Institutes for Quantum Science and Technology), Hiroyasu Tanigawa (National Institutes for Quantum Science and Technology), Yao Shen (Shanghai Jiao Tong Univ.), Takuya Nagasaka (National Institute of Fusion Science), Jingjie Shen (National Institute for Fusion Science), Mario Walter (Karlsruhe Institute of Technology), Emile Gaganidze (Karlsruhe Institute of Technology), Jarir Aktaa (Karlsruhe Institute of Technology), Shuhei Nogami (Tohoku University), Mitsuru Ohata (Osaka Univ.), Marta Serrano (CIEMAT), Rebeca Hernández (CIEMAT), David Andres (United Kingdom Atomic Energy Authority), Henk Nolles (United Kingdom Atomic Energy Authority), Yiqiang Wang (United Kingdom Atomic Energy Authority), Yutai Katoh (ORNL), Sehila Maria Gonzalez de Vicente (International Atomic Energy Agency (IAEA))
Specimen Size Effects on Creep Properties of F82H Reduced-Activation Ferritic Steel
Takuya Nagasaka (National Institute of Fusion Science), Jingjie Shen (National Institute for Fusion Science), Masami Ando (National Institutes for Quantum and Radiological Science and Technology), Taichiro Kato (National Institutes for Quantum and Radiological Science and Technology), Takashi Nozawa (National Institutes for Quantum and Radiological Science and Technology), Hiroyasu Tanigawa (National Institutes for Quantum and Radiological Science and Technology)
Flexural Testing of Neutron Irradiated Tungsten Materials by Three-Point Bend
Nathan C. Reid (Univ. Illinois, Urbana-Champaign), Lauren M. Garrison (ORNL), Trevor Marchhart (Penn State), Jean Paul Allain (Penn State)
Influence of Fatigue Precracking and Specimen Size on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels
Xiang Chen (ORNL), Marta Serrano (CIEMAT), Rebeca Hernández (CIEMAT), Mikhail A. Sokolov (ORNL)
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