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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|12:00–1:45PM EDT
Session Chair:
Robert P. Martin
Alternate Chair:
Dillon R. Shaver
Session Organizer:
Matthew D. Zimmer
Staff Producer:
Jessie Vazquez (ANS)
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Thermal Decomposition of Carbonates as a Passive Cooling Mechanism for Molten Salt Reactors
Christopher Forsyth (Univ. of California, Berkeley)
Paper
Study of Sodium Pool Fire Model Improvement in MELCOR for SFR
David L.Y. Louie (Sandia National Laboratories), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)
Thermal Hydraulic Modeling of the Kairos Power Generic Fluoride High Temperature Reactor in MELCOR
Robert F. Kile (Univ. of Tennessee Knoxville), Friederike Bostelmann (ORNL), Steve E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. of Tennessee Knoxville)
Modeling of HTTF test PG-26 using RELAP5-3D and SAM
Aaron Epiney (INL), Thanh Hua (ANL), James Wolf (INL), Ling Zou (ANL), Gerhard Strydom (INL), Rui Hu (ANL)
Safety Assessment of Composite Alternative Moderators for Modular High Temperature Gas-Cooled Reactors
Veronica Karriem (Univ. of Tennessee Knoxville), Edward M. Duchnowski (Univ. of Tennessee Knoxville), Nicholas R. Brown (Univ. of Tennessee Knoxville)
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