Response matrix based one group simulation model

The compact response matrix formalism and the modified thermal leakage correction model developed in this work have been incorporated into a one group nodal simulator, KINS2. The effectiveness and the adequacy of these methods used in KINS2 are demonstrated by performing various test problems for Korea nuclear Units. All the results performed to date show that this response matrix based one group nodal simulation accurately predicts core design parameters in an efficient manner. This efficient simulator is thus useful for LWR design calculations