MOX LTA Fuel Cycle Analyses: Nuclear and Radiation Safety

[摘要] Tasks of nuclear safety assurance for storage and transport of fresh mixed uranium-plutonium fuel of the VVER-1000 reactor are considered in the view of 3 MOX LTAs introduction into the core. The precise code MCU that realizes the Monte Carlo method is used for calculations.

[发布日期] 2001-09-28 [发布机构] Oak Ridge National Laboratory

[关键词] Novovoronezh-5 Reactor;Radiation Protection;Mixed Oxide Fuels;Fuel Cycle;11 Nuclear Fuel Cycle And Fuel Materials