Title of article :
Cosmos: a computer code to analyze LWR UO2 and MOX fuel up to high burnup
Author/Authors :
Koo، نويسنده , , Yang-Hyun; Lee، نويسنده , , Byung-Ho; Sohn، نويسنده , , Dong-Seong ، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1999
Abstract :
A computer code called COSMOS has been developed for the analysis of V02 and MOX fuel
during steady-state and transient operating conditions. The main purpose of the COSMOS is to
calculate temperature distribution in the fuel and cladding, and fission gas release from the
fuel. Experimental findings regarding such areas as rim effect and thermal conductivity
degradation with burnup are taken into account to analyze high burnup fuel. In addition, a
mechanistic fission gas release model developed based on physical processes is incorporated
into the code to calculate gas release during steady-state conditions. An empirical model
developed based on the amount of fission gas stored at the grain boundary is used for transient
operations. Another important feature of the COSMOS is that it can analyze fuel segments
refabricated from base-irradiated fuel rods. This feature makes it possible to utilize database
obtained from international projects such as HALDEN and RISO, many of which were collected
from refabricated fuel segments. Based on models for V02 fuel, MOX features such as change
in themo-mechanical properties and the effect of microscopic heterogeneity on fission gas
release have been taken into account. The capacity of the COSMOS has been tested with a
number of experimental results from some international fuel irradiation programs. This paper
provides a general description of the models contained in the COSMOS and some of the comparison
results between the calculations and measurements
Journal title :
Annals of Nuclear Energy
Journal title :
Annals of Nuclear Energy