Burnup calculation with different fission yield data
Fission yield is an important physical quantity to evaluate the amount of fission products after irradiation. The fission yield used in Japanese Evaluated Nuclear Data Library (JENDL) employs ENDF/B data. The fission yield has recently been evaluated in Japan based on the various theories. In order to evaluate the effect of different fission yield data on burnup calculation, burnup chain and/or fission yield data used in a burnup calculation is to be modified so as to obtain reasonable results because different/additional isotopes are stored among the data, especially for isomers.
The comparison between JENDL/FPY2011 and new fission yield evaluated by Tokyo Tech. was performed with SWAT4.0 for the PIE data: BM5 sample of Swiss Beznau-1 PWR, and the results shows that there is relatively large impact on the results. This shows the importance in burnup calculation how to handle the burnup chain and/or fission yield data on the comparison among different fission yield data.