[en] The main objective of this report is to evaluate the structural integrity accounting for creep and stress-rupture effect for the KALIMER reactor internal structures subjecting the normal reactor heat-up and cool-down transient operating cycles during 30 years of total life time. From the results of the structural damage evaluations, most parts of the reactor internal structures satisfy the limit rules of the structural integrity using ASME design code. However, the reactor baffle parts at elevation of the hot pool free surface slightly exceed the limit value of the total accumulated creep-ratcheting strain, then more detail structural analyses and evaluations for this region should be carried out to meet the design rules