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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
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
Jun 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Technical Session|Sponsored by IRD
Wednesday, November 18, 2020|12:00–2:10PM EST
Session Chair:
John Stillman (ANL)
Alternate Chair:
Cezary Bojanowski (ANL)
Session Organizers:
Erik Wilson (ANL)
Lin-Wen Hu
Track Organizer:
Staff Producer:
Rick Michal (American Nuclear Society)
This session will begin immediately after the conclusion of the session on New and Innovative Developments at the Research Reactors and Nuclear Science Programs. Papers for Progress on High-density LEU Fuel Development and Reactor Conversion-V will begin at approximately 12:10 PM CST.
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Thermal Analysis of Decay Heat Removal from a University of Missouri Research Reactor Discharged Low-Enriched Uranium Fuel Element
Dhongik S. Yoon (ANL), John A. Stillman (Argonne National Laboratory), Earl E. Feldman (Argonne National Laboratory), Erik H. Wilson (Argonne National Laboratory), Wilson Cowherd (ANL), Les P. Foyto (University of Missouri-Columbia Research Reactor), Kiratadas Kutikkad (University of Missouri-Columbia Research Reactor), Nickie J. Peters (University of Missouri-Columbia Research Reactor)
Paper
Formulas for Hot Channel Factors for Channels with Forced Flow
Jeremy R. Licht (Argonne National Laboratory), Mohammad Kalimullah (Argonne National Laboratory, Building 208, Room C150, Argonne, IL 60439), E. E. Feldman (Argonne National Laboratory, Argonne, IL 60439)
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