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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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April 2025
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Latest News
In an international industry, regulators cross the border too
Since nuclear physics works the same in Ontario as it does in Tennessee, the industry has been trying to create a reactor that can be deployed on both sides of the border. Now, the Nuclear Regulatory Commission and the Canadian Nuclear Safety Commission have decided that some of their rulings can cross the border too.
Nuclear Criticality Safety Division Topical Meeting (NCSD 2022)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Laguna A
Session Chairs:
Dale B. Lancaster
Olivier Ravat (Orano Melox)
Session Organizer:
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UF6 Cylinder Handling, Storage, and Transport at 8% Enrichment
James Banfield (Global Nuclear Fuel), Lon Paulson (Global Nuclear Fuel), Qi Ao (Boston Government Services)
Paper
Recent Assessments of Existing Transportation Packages for Use with HALEU Material
W.J. Marshall (ORNL), A. Lang (ORNL), E.M. Saylor (ORNL), R.A. Hall (EPRI)
Criticality Safety Implications of Extended-Enrichment and Accident-Tolerant Fuel for Fresh Fuel Storage
A.M. Shaw (ORNL), J.B. Clarity (ORNL)
Burnup Credit for PWR Spent Fuel Pools with High Enriched/High Burnup Fuel
Dale Lancaster (NuclearConsultants.com), Charles T. Rombough (CTR Technical Services)
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