2026-10-12T19:38:49Z https://www.scidb.cn/oai

10.57760/sciencedb.hjs.00700 2026-05-28T17:15:01Z

2026-05-28 Simulation data for “Verification of mitigation capability and procedure optimization for a small-break loss-of-coolant accident combined with loss of secondary-side cooling in the CPR1000 nuclear power plant”. doi:10.57760/sciencedb.hjs.00700 en This dataset contains the simulation results for “Verification of mitigation capability and procedure optimization for a small-break loss-of-coolant accident combined with loss of secondary-side cooling in the CPR1000 nuclear power plant”. The data were obtained from a “full-scope validation simulator” platform. The authors simulated an accident sequence for a specific unit under full-power operation, consisting of a 100 t/h cold-leg break in the primary loop, combined with failure of the auxiliary feedwater system to start up and loss of the cooling function of the turbine bypass system. By implementing operator actions strictly following the accident procedure, the transient responses of key safety parameters were obtained, including primary coolant system pressure, coolant inventory, core coolant temperature, fuel temperature, and containment pressure. After analyzing the results, the authors proposed adding a “monitoring module for the cooling function of the turbine bypass system (atmospheric discharge)” to the procedure. The accident was then simulated again using the optimized procedure. The dataset consists of nine files, which are, in order: trends of primary coolant system pressure and pressurizer water level; trends of primary coolant system pressure and pressurizer water level (repeated); trends of steam generator wide-range water level and secondary-side pressure; trends of maximum fuel center and cladding outer surface temperature; trends of containment pressure; trends of primary coolant system pressure and reactor pressure vessel water level (after procedure optimization); trends of maximum fuel cladding outer surface temperature (after procedure optimization); trends of maximum core outlet coolant temperature (after procedure optimization); and trends of containment pressure (after procedure optimization). These correspond to Figures 2, 3, 4, 5, 6, 8, 9, 10, and 11 of the associated paper, respectively. Nuclear power plant; Small-break loss-of-coolant accident; Secondary-side cooling loss; Mitigation capability verification; Procedure optimization zhang bo Zhang Zhenhua RESTRICTED dataset Science Data Bank