Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Joint U.S./Russian Progress Report for Fiscal Year 1997 Volume 2-Calculations Performed in the United States

Primm III, RT

Oak Ridge National Laboratory

关键词: Criticality;    Uranium;    Neutrons;    Mixed Oxide Fuels;    Progress Report;   

DOI  :  10.2172/814640
RP-ID  :  ORNL/TM-13603/V2
RP-ID  :  AC05-00OR22725
RP-ID  :  814640

美国|英语

来源: UNT Digital Library

【 摘 要 】

This volume of the progress report provides documentation of reactor physics and criticality safety studies conducted in the US 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 computational benchmarks and for those experimental benchmarks that the US and Russia mutually agreed in November 1996 were applicable to mixed-oxide fuel cycles for light-water reactors.