[en] This project which is titled as 'the impact assessment of power coefficient on CANDU safety and development of fundamental technology of numerical simulation' covers the following research study. At first, the investigation of various measurement data in order to develop the method to measure the CANDU power coefficient, development of a power maneuvering procedure to measure the PC in the actual operating CANDU system, uncertainty evaluation of power coefficient measurement using the uncertainty assessment regarding Xe and LZC reactivity changes by computer codes were performed. Also, three times Measurement and derivation of power coefficients according to the proposed test procedure were performed. At second, impact assessment of power coefficient on CANDU safety were perform by reviewing reactivity control characteristics of CANDU reactor compared to those of other types of reactors. And, sensitivity analysis of physics parameters were performed to evaluate the effect of power coefficient on safety analyses and the impact of higher PC on LBLOCA and LORC were performed by considering uncertainties of physics parameters regarding PC and integral impact assessment of power coefficient on CANDU safety were described. At third, one of proper Monte Carlo transport analysis codes, McCard code, was selected in order to develop Monte Carlo model for CANDU reactor core. By using McCard code, it was performed the benchmark problem suite for reactor physics study of LWR next generation fuels and the results calculated by McCARD and WIMS-IST for the CANDU bundle problem were compared together in terms of k-infinite and isotopic number densities over burnup. Also, Monte Carlo analysis code system as well as the input model for CANDU core were preliminarily developed