Calculation Analysis of San Onofre Depletion MOX Fuel Experiment

Pavlovichev, AM

Oak Ridge National Laboratory

关键词: Uranium Isotopes;    99 General And Miscellaneous//Mathematics, Computing, And Information Science;    Isotope Ratio;    Mixed Oxide Fuels;    Computer Calculations;   

DOI  :  10.2172/814488
RP-ID  :  ORNL/SUB/00-85B99398V-8
RP-ID  :  AC05-00OR22725
RP-ID  :  814488

美国|英语

来源: UNT Digital Library

【 摘 要 】

The report provides calculation results of isotopic composition of spent MOX fuel irradiated in Sun Onofre PWR reactor. The calculation was performed by means of the MCU/BURNUP Monte Carlo code. The code is developed in Kurchatov Institute, Russia. The predicted isotope contents are compared with the measured ones. A purpose of this work is a verification both the code and the model of experiment description. Predicted plutonium content exceeds the measured one approximately by 3%. It is arise mainly from error of {sup 239}Pu isotope. Isotopic contents of the main plutonium and uranium isotopes are predicted with satisfactory precision.