Safety analysis on the operational transients and some accidents of MUTSU reactor

The safety analyses on the operational transients and accidents of the MUTSU reactor have been described. The purposes of the analysis are: 1) to show the safety of the MUTSU reactor and 2) to provide the information of the methods of general transient analysis of LWR using RETRAN and other computer programs. This report gives analytical results on the following items of transients and accidents: (1) Partial loss of primary coolant flow (2) Loss of feedwater to steam generator (3) Excessive feedwater to steam generator (4) Blackout (5) Loss of primary coolant flow accident (6) Main coolant pump stick accident (7) Feedline pipe rupture accident (8) Steam generator U-tube rupture accident. The results shows the maximum pressure of primary system is 139.4 kg/cm2G (1997 psia) and minimum DNBR is 2.01, and the MUTSU-reactor has enough margin with respect to the safety limits. The useful informations on the modeling technique and analytical method are also obtained. (author)