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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
Latest Magazine Issues
Apr 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Technical Session
Friday, April 9, 2021|11:00AM–12:30PM EDT
Session Chair:
Ghada Shkoukani (NCSU)
Alternate Chair:
Ishita Trivedi
Session Organizer:
Edward Chen (NCSU)
Track Organizer:
Session Producers:
William Dawn (NCSU)
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Refutation of Pooled Analysis Supporting Linear No-Threshold Model
Matthew J. Sawyers (U.S. Department of Energy), Robert B. Hayes (North Carolina State University)
Paper
Shielding of a Reactor Startup Neutron Source
Trevor Casper (University of Idaho)
Shielding for the ZEUS Laser Facility
Colton W. Graham (University of Michigan), Emma Guerin (University of Michigan), Igor Jovanovic (University of Michigan)
Parameter Studies of Neutron Ambient Dose Equivalent Conversion Coefficients Computed with the MCNP6.2 Code
Madeline I. Prince (United States Naval Academy), Marshall Millett (United States Naval Academy), Steve McHale (United States Naval Academy)
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