Browsing by Subject "MCNP 6.1 Beta"
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Increasing the fuel cycle length of a PWR by means of a homogeneous uranium, thorium and plutonium fuel design
(North-West University (South Africa) , Potchefstroom Campus, 2016)In this study a new homogeneous fuel pellet was designed for a Pressurized Watercooled Reactor (PWR), aimed at increasing its fuel cycle length. The standard 4.5 wt. % Low Enriched Uranium (LEU) fuel pellet of the South ...