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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
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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|Modeling, Analysis, and Methods
Tuesday, October 11, 2022|10:15–11:55AM EDT|Branle
Session Chair:
Ian Porter (GE)
Alternate Chair:
Chao Wang (Framatome)
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Assessing New Accident Tolerant Fuel and Cladding Models in the Fuel Performance Code Bison
10:15–10:40AM EDT
Gyanender Singh (INL), Yifeng Che (INL), Kyle Gamble (INL), Aysenur Toptan (INL), Jason Hales (INL), Stephen Novascone (INL)
Paper
Fuel Performance Analysis of Cr-Coated Fuel During Startup and Normal Operation of LWRs Using FEMAXI-8
10:40–11:05AM EDT
Soki Dehara (Waseda Univ.), Akifumi Yamaji (Waseda Univ.), Yoshiyuki Nemoto (Japan Atomic Energy Agency), Shinichiro Yamashita (Japan Atomic Energy Agency)
Out-Of-Reactor Creep Analysis of Chromium Surface-Coated Optimized ZIRLO™ Cladding
11:05–11:30AM EDT
J.M. Vidal (ENUSA Industrias Avanzadas), I. del Río (ENUSA Industrias Avanzadas), J. Walters (Westinghouse Electric Co.), Y. Long (Westinghouse Electric Co.), O. Linsuain (Westinghouse Electric Co.)
PCMI Analyses of SiC Cladded Fuel During BWR LOCA with FEMAXI-ATF
11:30–11:55AM EDT
Yutaka Nakao (Waseda Univ.), Akifumi Yamaji (Waseda Univ.), Yoshiyuki Nemoto (Japan Atomic Energy Agency), Shinichiro Yamashita (Japan Atomic Energy Agency)
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