Design Studies of ``100% Pu'' Mox Lead Test Assembly

Pavlovichev, A.M.

Oak Ridge National Laboratory

关键词: Wwer-5 Reactor;    Mixed Oxide Fuels;    Kinetics;    Computer Calculations;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/777711
RP-ID  :  ORNL/SUB/99-B99398V-4
RP-ID  :  AC05-96OR22464
RP-ID  :  777711

美国|英语

来源: UNT Digital Library

【 摘 要 】

In this document the results of neutronics studies of <<100%Pu>> MOX LTA design are presented. The parametric studies of infinite MOX-UOX grids, MOX-UOX core fragments and of VVER-1000 core with 3 MOX LTAs are performed. The neutronics parameters of MOX fueled core have been performed for the chosen design MOX LTA using the Russian 3D code BIPR-7A and 2D code PERMAK-A with the constants prepared by the cell spectrum code TVS-M.