Open AccessNeutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Joint US/Russian Progress Report for Fiscal 1997. Volume 3 - Calculations Performed in the Russian Federation
Publication year - 1998
Language(s) - English
Resource type - Reports
DOI - 10.2172/652930
Subject(s) - plutonium , fissile material , mox fuel , national laboratory , stockpile , plutonium 240 , spent nuclear fuel , nuclear engineering , nuclear weapon , environmental science , waste management , actinide , engineering , plutonium 239 , radiochemistry , chemistry , nuclear physics , nuclear chemistry , physics , neutron , engineering physics , fission
This volume of the progress report provides documentation of reactor physics and criticality safety studies conducted in the Russian Federation during fiscal year 1997 and sponsored by the Fissile Materials Disposition Program of the US Department of Energy. Descriptions of computational and experimental benchmarks for the verification and validation of computer programs for neutron physics analyses are included. All benchmarks include either plutonium, uranium, or mixed uranium and plutonium fuels. Calculated physics parameters are reported for all of the contaminated benchmarks that the United States and Russia mutually agreed in November 1996 were applicable to mixed-oxide fuel cycles for light-water reactors