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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
Alex Galperin, Meir Segev, Anatoly Goldfeld, Yonathan Karni
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 354-363
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A15962
Articles are hosted by Taylor and Francis Online.
The independently developed and verified computational system BGUCORE for the neutronic analysis of pressurized water reactor cores is introduced. The basic methodology adopted generates cross-section libraries for each fuel type as functions of burnup and soluble boron concentrations. These cross sections are arranged as a two-dimensional matrix of sets, each set corresponding to a particular burnup/boron pair of coordinates. The two-dimensional diffusion analysis of the reactor core utilizes the pregenerated libraries by interpolating between burnup and boron entry points. The present system is especially designed for the analysis of cores with burnable poisons. Such cores are characterized by strong heterogeneity and selfshielding effects. Detailed benchmark calculations, performed for cycle 1 of the Zion 2 power station, validate the performance of the BGUCORE system. Further development of the system, aimed at creating a comprehensive design and fuel cycle analysis tool, includes a three-dimensional representation of the core and thermohydraulic modules.