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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
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Technical Session|Sponsored by THD
Wednesday, June 10, 2020|4:35–6:20PM EDT
Session Chair:
Prashant Jain (ORNL)
Session Organizer:
Elia Merzari
Track Organizer:
Igor Bolotnov (NCSU)
Staff Producer:
Janice Lindegard (American Nuclear Society)
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Validation of the 1-D Thermal Stratification Model in Gallium Environment
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Brendan Ward (Kansas State Univ.), Hitesh Bindra (Kansas State Univ.)
Paper
Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core
Justin Weinmeister, Prashant K. Jain
Multi-Scale & Multi-Physics Analysis of PWR Steam Line Break Accident
Jae Ryong Lee (KAERI), Han Young Yoon (KAERI), Ik Kyu Park (KAERI)
Sodium Fire Models for In- and Ex-vessel Safety Analysis Code SPECTRA
Mitsuhiro Aoyagi (Japan Atomic Energy Agency), Akihiro Uchibori (Japan Atomic Energy Agency), Takashi Takata (Japan Atomic Energy Agency), Hiroyuki Ohshima (Japan Atomic Energy Agency)
Code Validation for SBLOCA Test of PHWR using MARS-KS
Kyunglok Baek (Korea Institute of Nuclear Safety), Seon Oh Yu (Korea Institute of Nuclear Safety)
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