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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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
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 MSTD
Wednesday, June 14, 2023|3:15–5:00PM EDT|Marriott 10
Session Chair:
Jake R. Quincey
Session Organizer:
Alternate Chair:
Kenneth J. Geelhood
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Microstructural Analysis of a Zr Rich Specimen from the Central Radial Region of a Neutron Irradiated U-10Zr Fuel
3:15–3:35PM EDT
N. Rodriguez Perez (Purdue), J. Thomas (Purdue), M.A. Okuniewski (Purdue)
Paper
Experiments Supporting Effective Thermal Conductivity Calculation of Irradiated U-Zr Fuel
3:35–3:55PM EDT
Cynthia Adkins (INL), Daniele Salvato (INL), Tiankai Yao (INL), Yong Yang (Univ. Florida)
Impact of Fabrication Techniques on U-10wt%Mo Fuel Microstructure Irradiated to Low Burnup
3:55–4:15PM EDT
Sukanya Majumder (Purdue), Gyuchul Park (ANL), Daniel Murray (INL), Benjamin Beeler (NCSU), Maria A. Okuniewski (Purdue)
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