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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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Nuclear Science and Engineering
Fusion Science and Technology
Framatome to work with Romania’s Nuclearelectrica on Lu-177 production
Framatome and Nuclearelectrica, operator of Romania’s Cernavoda nuclear power plant, announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope lutetium-177. The cooperative agreement was signed during the World Nuclear Exhibition 2023, held November 28–30 in Paris.
Technical Session|Sponsored by MSTD
Tuesday, November 15, 2022|3:15–5:00PM MST|Kaibab
J. Rory Kennedy
Jake R. Quincey
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Sensitivity Analysis of TRISO Fuel Configuration in a MiniFuel Irradiation Experiment
Jacob P. Gorton (ORNL), Zane G. Wallen (ORNL), Annabelle G. Le Coq (ORNL), Christian M. Petrie (ORNL), Kory D. Linton (ORNL), Tyler J. Gerczak (ORNL)
Preliminary Data and Thermal Modeling of In Situ Wireless Sensor Irradiation in the High Flux Isotope Reactor
Padhraic L. Mulligan (ORNL), Kara Godsey (ORNL), Daniel C. Sweeney (ORNL), A. Shay Chapel (ORNL), N. Dianne B. Ezell (ORNL), Shawn Stafford (Westinghouse Electric Co.), Jeffrey Arndt (Westinghouse Electric Co.), Jorge Carvajal (Westinghouse Electric Co.), Christian M. Petrie (ORNL)
Analysis of Degraded G-348 Graphite used in the High Temperature Test Facility
Sutapa Biswas (Idaho State), Daniel LaBrier (Idaho State), Izabela Gutowska (Oregon State), Brian Woods (Oregon State)
High-Temperature Furnace Testing of Corrosion-Resistant Coatings for Advanced Reactors
William T. Searight (Penn State), Leigh Winfrey (SUNY Maritime College)
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