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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Nominations open for CNTA awards
Citizens for Nuclear Technology Awareness is accepting nominations for its Fred C. Davison Distinguished Scientist Award and its Nuclear Service Award. Nominations for both awards must be submitted by August 1.
The awards will be presented this fall as part of the CNTA’s annual Edward Teller Lecture event.
Technical Session|Sponsored by IRD
Tuesday, November 17, 2020|12:00–2:10PM EST
Session Chair:
Laura Jamison (ANL)
Alternate Chair:
Bei Ye (ANL)
Session Organizers:
Erik Wilson (ANL)
Lin-Wen Hu
Track Organizer:
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Fluid Structure Interaction Analysis for Involute Fuel Plates
Jeremy R. Licht (Argonne National Laboratory), Yiqi Yu (Argonne National Laboratory), Marta Sitek (Argonne National Laboratory), Aurelien X. Bergeron (Argonne National Laboratory), Cezary Bojanowski (Argonne National Laboratory)
Paper
Review of the Technical Basis for Properties and Fuel Performance Data Used in USHPRR HEU to LEU Conversion Analysis Compared to the Preliminary UMo Report
Erik H. Wilson (Argonne National Laboratory), David Jaluvka (Argonne National Laboratory), Walid Mohamed (Argonne National Laboratory), John A. Stillman (Argonne National Laboratory), Laura M. Jamison (Argonne National Laboratory)
Microstructural Evolutions and Thermal Conductivity Degradation on Al-UMo Interface Irradiated by Swift Heavy Ions
Kun Mo (Argonne National Laboratory), Abdellatif M. Yacout (Argonne National Laboratory), S. Sinha (University of Illinois at Urbana-Champaign), M.C. Rajagopal (University of Illinois at Urbana-Champaign), L.A. Nimmagadda (University of Illinois at Urbana-Champaign), J. Shi (Technical University of Munich), Bei Ye (Argonne National Laboratory), Yinbin Miao (Argonne National Laboratory)
Research and Test Reactor Fuel Modeling and Simulation with DART
Bei Ye (Argonne National Laboratory), Aaron Oaks (Argonne national laboratory)
Preliminary Assessment of Structural Behavior of MITR Low-Enriched Uranium Fuel Plates
Erik H. Wilson (Argonne National Laboratory), Cankur F. Cetinbas (Argonne National Laboratory), Hee S. Roh (Argonne National Laboratory), Walid Mohamed (Argonne National Laboratory)
Computational Modeling of the Cheverton and Kelley Experimental Analysis of HFIR Fuel Plate Deflections
Yiqi Yu (Argonne National Laboratory), Jeremy R. Licht (Argonne National Laboratory), Cezary Bojanowski (ANL), Aurelien X. Bergeron (Argonne National Laboratory), Marta Sitek (ANL)
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