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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!
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Nuclear Science and Engineering
December 2024
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November 2024
Latest News
Site acquired for GLE laser enrichment plant
Global Laser Enrichment (GLE) has acquired a 665-acre parcel of land for its planned Paducah Laser Enrichment Facility (PLEF) in Kentucky.
Micheal A. Smith, Richard M. Lell, Gerardo Aliberti, Zhaopeng Zhong, Florent Heidet
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S71-S82
Technical Paper | doi.org/10.1080/00295639.2022.2058845
Articles are hosted by Taylor and Francis Online.
The Versatile Test Reactor (VTR) that is being designed today is heavily reliant upon the Argonne Reactor Codes (ARC) modeling software for predicting the operational performance of the VTR. Given its usage in the VTR, a set of validation cases appropriate for the VTR must be assembled. The measurements taken in ZPPR-15, Experimental Breeder Reactor II (EBR-II), and Fast Flux Test Facility were chosen and analyzed with the ARC software as part of creating the necessary validation basis. The results of the ARC software on the measured data are discussed here, and they demonstrate the accuracy of the ARC software on fast spectrum reactors.
