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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nov 2024
Jul 2024
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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
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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