VENUS-2 MOX Core Benchmark: Results of ORNL Calculations Using HELIOS-1.4

Ellis, RJ

Oak Ridge National Laboratory

关键词: Economics;    Plutonium Recycle;    Mixed Oxide Fuels;    Wwer Type Reactors;    Pwr Type Reactors;   

DOI  :  10.2172/777637
RP-ID  :  ORNL/TM-2000/180
RP-ID  :  AC05-96OR22464
RP-ID  :  777637

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Task Force on Reactor-Based Plutonium Disposition, now an Expert Group, was set up through the Organization for Economic Cooperation and Development/Nuclear Energy Agency to facilitate technical assessments of burning weapons-grade plutonium mixed-oxide (MOX) fuel in U.S. pressurized-water reactors and Russian VVER nuclear reactors. More than ten countries participated to advance the work of the Task Force in a major initiative, which was a blind benchmark study to compare code benchmark calculations against experimental data for the VENUS-2 MOX core at SCK-CEN in Mol, Belgium. At the Oak Ridge National Laboratory, the HELIOS-1.4 code was used to perform a comprehensive study of pin-cell and core calculations for the VENUS-2 benchmark.