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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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.