Power-Burnup Data of 37-element Fuel Bundle for Safety Analysis

The calculation of the inventory and distribution of the fission product during the normal operating period is a primary step for an evaluating the release of fission gas into a coolant or moderator after the postulated accident of single channel or the LOCA. The fission product inventory is dependent on the power and burnup history of the fuel, therefore, making the power history data of the each fuel element is the basic work in the accident analysis. In this report, the limit channel is assumed that has the maximum limit channel and bundle powers. For the assumed limit channel, the element's linear power and burnup histories are produced to predict the fission product inventory and to analyze the performance of fuel during the normal operation