Depletion Analysis Of Research Reactor For Core Conversion:HEU TO LEU. A standardized depletion calculation for reactor core conversion fueled with 19.75% enriched UO2 using the VENTURE code

      Аннотация: This book contains a step by step detailed information on the depletion calculation for the core conversion studies of research reactor. It provides information for the computation of volume to moderator per fuel pin for the fuel cell. The operational age of the designed reactor system when fueled with the proposed UO2 material enriched to 19.75% U235 was also determined.In addition, the changes in fission product and in fissile isotope in the core of NIRR-1 were all generated. This results can serve as a very useful tool in the design of a research reactor using the proposed LEU fueled for NIRR-1.

Ключевые слова: Depletion, Reactor, fuel, venture, Fission, Fussion, Reactivity, lump, Burnup.