San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses

The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium
isotopes) discharged from reactors is of interest to the Fissile Material Disposition Program. The
validation of depletion codes used to predict isotopic compositions of MOX fuel, similar to studies
concerning uranium-only fueled reactors, thus, is very important. The EEI-Westinghouse Plutonium
Recycle Demonstration Program was conducted to examine the use of MOX fuel in the San Onofre
PWR, Unit I, during cycles 2 and 3. The data, usually required as input to depletion codes, either
one-dimensional or lattice codes, were taken from various sources and compiled into this report.
Where data were either lacking or determined inadequate, the appropriate data were supplied from
other references. The scope of the reactor operations and design data, in addition to the isotopic
analyses, was considered to be of sufficient quality for depletion code validation.