[en] Safety analysis for the conceptual design of KALIMER-600 in previous step was carried out for the ATWS using SSC-K code under the bounding approach. But the safety analysis is difficult to assess the safety of the system that consider correct design characteristics. KALIMER safety analysis team develops the new system transient analysis code MARS-LMR and the code was applied to the safety analysis of the typical DBEs. Accidents in a pool-type sodium-cooled fast reactor can mainly be classified to a Transients of over-power, a Loss of flow, a Loss of heat sink, Pipe break in the primary system, Sodium leak at the primary sodium boundary, and Station black out. This report describes the analysis results for the above DBEs, sensitivity calculation results for the transients of over power, and the analysis for long term cooling of the loss of heat sink. The DBEs analysis results reveals that the KALIMER-600 design satisfy the safety limit for all events except the case of sodium leak at the primary sodium boundary which requires other safety system than PDRC system. In the sensitivity calculation results, the effect of a variable of power on a temperature is relatively large compared to variables of reactivity feedback coefficients and primary flow rate. In a long term cooling analysis, it is indicated to consider a active safety system because the long time period is required to take the reactor to hot standby conditions