Design Studies of ''Island'' Type MOX Lead Test Assembly

Pavlovitchev, A.M.

Oak Ridge National Laboratory

关键词: Novovoronezh-5 Reactor;    Computerized Simulation;    Mixed Oxide Fuels;    11 Nuclear Fuel Cycle And Fuel Materials;    Fuel Assemblies;   

DOI  :  10.2172/814133
RP-ID  :  ORNL/SUB/99-B99398V-3
RP-ID  :  AC05-00OR22725
RP-ID  :  814133

美国|英语

来源: UNT Digital Library

【 摘 要 】

In this document the results of neutronics studies of <> type MOX LTA design are presented. The characteristics both for infinite MOX grids and for VVER-1000 core with 3 MOX LTAs are calculated. the neutronics parameters of MOX fueled core have been performed using the Russian 3D code BIPR-7A and 2D code PERMAK-A with the constants prepared by the cell spectrum code TVS-M.