Shipping Cask Studies with MOX Fuel

Pavlovichev, A.M.

Oak Ridge National Laboratory

关键词: Novovoronezh-5 Reactor;    Mixed Oxide Fuels;    Casks;    Radiation Protection;    42 Engineering;   

DOI  :  10.2172/814306
RP-ID  :  ORNL/SUB/00-85B99398V-3
RP-ID  :  AC05-00OR22725
RP-ID  :  814306

美国|英语

来源: UNT Digital Library

【 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.