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

Abstract

The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) 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, were considered to be of sufficient quality for depletion code validation.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (US)
Sponsoring Org.:
USDOE Office of Fissile Materials Disposition (MD) (US)
OSTI Identifier:
12456
Report Number(s):
ORNL/TM-1999/108
TRN: US0102520
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 1 Sep 1999
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; SAN ONOFRE-1 REACTOR; MIXED OXIDE FUELS; PLUTONIUM RECYCLE; REACTOR OPERATION; URANIUM; ISOTOPE RATIO; MATHEMATICAL MODELS; VALIDATION; BURNUP

Citation Formats

Hermann, O.W. San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses. United States: N. p., 1999. Web. doi:10.2172/12456.
Hermann, O.W. San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses. United States. doi:10.2172/12456.
Hermann, O.W. Wed . "San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses". United States. doi:10.2172/12456. https://www.osti.gov/servlets/purl/12456.
@article{osti_12456,
title = {San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses},
author = {Hermann, O.W.},
abstractNote = {The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotope) 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, were considered to be of sufficient quality for depletion code validation.},
doi = {10.2172/12456},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1999},
month = {9}
}