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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Sponsored by Integrated Phenomena in Reactor Materials
Wednesday, December 13, 2023|10:00–11:40AM CST|Galerie 5
Session Chair:
Haozheng Qu (Purdue Univeristy)
Alternate Chair:
Andrew K. Hoffman (n/a)
Track Organizers:
Adrian Couet (University of Wisconsin- Madison)
Stu Maloy (PNNL)
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FeCrAl Fuel Clad Chemical Interaction in Light Water Reactor Environments
10:00–10:20AM CST
Haozheng J.Qu (GE Global Research), Maria Higgins (Penn State), Hamdy Abouelella (GE Global Research), Fabiola Cappia (INL), Jatuporn Burns (INL), Lingfeng He (INL), Caleb Massey (ORNL), Jason Harp (ORNL), Rajnikant V. Umretiya (GE Research Center), Andrew K. Hoffman (GE Research Center), Janelle Wharry (Purdue), Raul B. Rebak (GE Global Research)
Paper
Integral Irradiation Testing and Post Irradiation Examination Programs for Accident Tolerant Fuel Development at Idaho National Laboratory
10:20–10:40AM CST
D.W. Kamerman (INL), B.P. Durtschi (INL), N.S. Oldham (INL), N.E. Woolstenhulme (INL), F. Cappia (INL), R.S. Hansen (INL), A.W. Colldeweih (INL), P.G. Petersen (INL)
Presentation Slides (Visible to Attendees) — Slides
Development and Preliminary Testing of an Internal Pressure Fatigue Test Rig for Accident Tolerant Fuel Cladding
10:40–11:00AM CST
Q. Cheng (Canadian Nuclear Laboratories), H.M Nordin (Canadian Nuclear Laboratories), C. Zhang (Canadian Nuclear Laboratories), T. Molnar (Canadian Nuclear Laboratories), R. Lungu (Canadian Nuclear Laboratories)
Effect of Surface Damage on Corrosion of Zr Alloys
11:00–11:20AM CST
B. Ensor (Naval Nuclear Laboratory), A. Lucente (Naval Nuclear Laboratory), R. Morris (Naval Nuclear Laboratory), J. Sutliff (Naval Nuclear Laboratory)
Presentation Slides (Visible to Attendees)
Phase-Field Modeling for the High-Temperature Zirconium Oxidation
11:20–11:40AM CST
Jiho Kim (Kyung Hee Univ.), Kunok Chang (Kyung Hee Univ.)
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