Shipping Cask Studies with MOX Fuel.

Pavlovichev, A. M.

Technical Information Center Oak Ridge Tennessee

关键词: Casks;    Transportation;    Nuclear fuels;    Mixed oxide fuels;   

RP-ID  :  DE2001786762

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports 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 new of 3 MOX LTAs introduction into the core. The precise code MCU that realizes the Monte Carlo method is used for calculations.