San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses -- Revision 1

Hermann, O.W.

Oak Ridge National Laboratory

关键词: Reactor Operation;    Uranium;    Plutonium Isotopes;    Plutonium Recycle;    Mixed Oxide Fuels;   

DOI  :  10.2172/814624
RP-ID  :  ORNL/TM-1999/108/R1
RP-ID  :  AC05-00OR22725
RP-ID  :  814624

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来源: UNT Digital Library

【 摘 要 】

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.