ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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
Aug 2022
Jan 2022
Latest Journal Issues
Nuclear Science and Engineering
September 2022
Nuclear Technology
Fusion Science and Technology
August 2022
Latest News
American Nuclear Society supports IAEA’s condemnation of attack on Ukraine nuclear power plant
Statement from American Nuclear Society President Steven Arndt and Executive Director and CEO Craig Piercy:
Technical Session|Sponsored by THD
Wednesday, June 16, 2021|3:30–5:15PM (4:30–6:15PM EDT)
Session Chair:
Elia Merzari
Alternate Chair:
Guillaume P. Mignot
Session Organizer:
Yassin A. Hassan
Staff Producer:
Jessie Vazquez (ANS)
To access the session recording, you must be logged in and registered for the meeting.
Register NowLog In
To access paper attachments, you must be logged in and registered for the meeting.
Preliminary Safety Analysis Results of Lead Cooled Fast Reactor: MicroURANUS under Unprotected Loss of Flow Condition
Ji Yong Kim (Ulsan Nat'l Institute of Science and Technology), In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)
Summary
Numerical Study of the Heat Transfer in Randomly Packed Spheres for Fluoride Salt Cooled High-Temperature Reactors (FHRs)
Scott Wahlquist (Idaho State Univ.), Amir Ali (Idaho State Univ.)
Unified Domain Knowledge Informed Machine Learning Model for CHF Prediction
Yue Jin (MIT), Xingang Zhao (ORNL), Koroush Shirvan (MIT)
To join the conversation, you must be logged in and registered for the meeting.