A data set of the analysis of mechanical seal of residual heat-removal pump

Residual heat removal pump (RRA pump) is a core equipment used to remove radioactive decay heat from the core and maintain thermal balance in the primary loop during nuclear reactor shutdown. Its sealing and structural integrity directly affect the safe and stable operation of nuclear power plants. Therefore, it is necessary to evaluate the leakage rate of mechanical seals of RRA pumps under thermal shock. By establishing a three-dimensional model of the RRA pump and its mechanical seal in a nuclear power plant, the unidirectional thermal fluid solid coupling method was used to calculate and analyze the internal flow field and temperature field of the RRA pump and mechanical seal under specific operating conditions. The axial deformation of the mechanical seal was obtained, and the leakage characteristics of its main sealing area were analyzed. The analysis results show that due to the frictional heat generated by the dynamic and static ring end faces of the mechanical seal and the flushing of cooling water, the temperature of the sealing end face first increases and then decreases in the radial direction, resulting in a narrow middle and wide ends of the leakage channel of the sealing end face. The calculated mechanical seal leakage rate is basically consistent with the actual operating conditions of a nuclear power plant. The research results provide an accurate numerical simulation method for evaluating the sealing performance of RRA pumps in the reactor primary loop, which has practical engineering significance.