Open AccessVerification Calculation Results to Validate the Procedures and Codes for Pin-by-Pin Power Computation in VVER Type Reactors with MOX Fuel Loading
Author(s) -
Z.N. Chizhikova,
A.G. Kalashnikov,
E.N. Kapranova,
V.E. Korobitsyn,
G. N. Manturov,
A. M. Tsiboulia
Publication year - 1998
Language(s) - English
Resource type - Reports
DOI - 10.2172/3122
Subject(s) - mox fuel , burnup , nuclear engineering , uranium dioxide , neutron capture , nuclear fuel , spent nuclear fuel , neutron flux , vver , neutron , materials science , uranium , nuclear physics , engineering , physics