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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|Sponsored by RPD
Wednesday, November 20, 2024|8:00–9:45AM EST|Biscayne 1
Session Chair:
Shane G. Stimpson (BWX Technologies)
Alternate Chair:
John Bess (JFoster and Assoc.)
Session Organizer:
Zeyun Wu (Virginia Commonwealth Univ.)
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Development of the ENDF/B-VII.1 and VIII.0 AMPX 61- and 258-Group Libraries for SCALE 7.0/Polaris LWR Analysis
8:00–8:20AM EST
Kang Seog Kim (ORNL), Dorothea Wiarda (ORNL), Byoung-Kyu Jeon (ORNL), William A. Wieselquist (ORNL)
Paper
Development of an Advanced Cross-Section Model Including Control Rod Depletion
8:20–8:40AM EST
Jinsu Park (Ulsan Nat'l Institute Science and Technology), Wisoo Jeong (KEPCO Nuclear Fuel), Changhyun Lim (KEPCO Nuclear Fuel), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Error Propagation Analysis, from LWR Assemblies to Plants, Using SCALE/Polaris-PARCS with the ENDF/B-VII.1 and VIII.0 AMPX 56-Group Libraries
8:40–9:00AM EST
Kang Seog Kim (ORNL), William A. Wieselquist (ORNL)
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