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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
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!
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August 2024
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Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Jason B. Meng, Francesco Deleo (TerraPower)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 51-59
The TerraPower-developed mechanical analysis code OXBOW is used to evaluate the mechanical performance of Traveling Wave Reactor core assemblies. Benchmarking work was performed using OXBOW to compare displacement and contact load results against a variety of mechanical analysis codes from the International Working Group on Fast Reactors (IWGFR) for a set of well-defined assembly conditions. Significant differences in results were found in the benchmark problem modeling a thermally bowing row of assemblies in a limited free bow core restraint configuration. This is due to a bridging effect which occurs due to differences in contact modeling methodology. Additionally, significant displacement differences in results were found in the benchmark problem modeling duct dilation under internal pressure, temperature, and irradiation. These differences are due to the fact that OXBOW dilation models account for both stress relaxation and geometric nonlinearities. Differences in results between OXBOW and the IWGFR benchmark participants are attributed to higher fidelity models generated using OXBOW.