Comparative sensitivity study of the RBMK-1500 reactor one group distribution header blockage accident model

The article presents comparative sensitivity study of the Ignalina NPP RBMK-1500 reactor one group distribution header complete blockage accident model. The accident model was developed by RELAP5 thermal-hydraulic code and the accident scenario is one of the scenarios analyzed in the RBMK reactor safety analysis report. The sensitivity study comprised of the Fourier amplitude sensitivity test and the random sample based sensitivity measures (correlation coefficients and standardized regression coefficients). Two types of the model output were investigated: maximum temperature and dynamic temperature change during the progression of the accident. In addition, the effect of the input parameter distribution of different truncation levels and the effect of double standard deviation to the sensitivity results were studied.