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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Chenglin Zhu, Yuhang Yan, Shuo Li, Hui Yu (SPICRI)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 732-737
The cosLATC is a multi-group two-dimensional lattice code developed by SNPSDC, which is an essential part in the COSINE(Core and System Integrated Engine) code package. Resonance self-shielding calculation is a very important part in the reactor physics calculation. It provides effective cross section for the next transport calculation. Traditional two-region resonance calculation method based on equivalence theory was developed in the cosLATC code. However, for the fuel pin which contains strong resonance self-shielding effect or huge absorption cross section nuclides, the spatial variation of the self-shielding effect is crucial to determine its radial power distribution. The equivalence theory assumes a spatially constant cross section within the fuel region and cannot evaluate spatially dependent resonance self-shielding effect. So the SDDM (Spatially Dependent Dancoff Method) self-shielding resonance was developed in the latest version of cosLATC which can split the fuel pellet into arbitrary number of annuli and generate the effective cross section for every annulus. A serial of benchmarks are calculated to verify this new resonance self-shielding module were performed. These benchmarks include different assembly problems of Watts Bar benchmark and critical benchmarks. The results show that the new resonance self-shielding module is capable of modeling the resonance self-shielding in a variety of PWR benchmarking cases, including difficult fuel lattice cases with poison, control rods or mixed gadolinia fuel rods. The critical calculation results can be accepted for the lattices which the conditions vary with the enrichment, radius of fuel rods, lattices pitch and experimental buckling.