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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Technical Session|Sponsored by ETWDD
Tuesday, November 15, 2022|1:00–2:45PM MST|Acacia
Session Chair:
Julie Jacobson (NEUP/INL)
Alternate Chair:
Andrew E. Thomas (NEUP)
Session Organizer:
Andrew E. Thomas (INL)
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Low-Temperature Cladding Failure During a R.I.A Transient for High-Burnup Fuels
1:00–1:20PM MST
Luiz C. Aldeia Machado (Penn State), Elia Merzari (Penn State), William J. Walters (Penn State)
Paper
Fuel Performance Uncertainty Quantification and Sensitivity Analysis Methodology for Aleatoric and Epistemic Sources of Uncertainties
1:20–1:40PM MST
Quentin Faure (NCSU), Gregory Delipei (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU), Alessandro Petruzzi (NINE)
Swelling Behavior of a Clay-Pellets Mixture Intended for the Isolation of Spent Nuclear Fuel
1:40–2:00PM MST
Abdulvahit Sahin (TAMU), Roa'a AL-Masri (TAMU), Marcelo Sanchez (TAMU), Yongliang Xiong (Sandia), Thomas Dewers (Sandia), Edward N. Matteo (Sandia)
Pelletized Clay Mixtures with Enhanced Thermal Conductivity Intended for the Isolation of High-Level Nuclear Waste
2:00–2:20PM MST
Roa'a AL-Masri (TAMU), Abdulvahit Sahin (TAMU), Marcelo Sanchez (TAMU), Yongliang Xiong (Sandia), Thomas Dewers (Sandia), Edward N. Matteo (Sandia)
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