Study on Helium Leak Detection System for Heat Transfer Tube of Steam Generator in Nuclear Power Plant

This study introduces the principle and system composition of the in-service helium leakage detection system of the heat transfer tube of steam generator in a nuclear power plant, and simulates the leakage detection test of the heat transfer tube during the in-service overhaul of the steam generator in a nuclear power plant. The test results show that the optimal parameters can be set as follows: the helium concentration share of the secondary side of the steam generator is 30%; the pumping rate is 20 L/min; the secondary side pressure of the steam generator is 0.6 MPa; the system leaking point location error is within 0.5 m. The helium leakage detection system of heat transfer tube of steam generator studied in this paper can provide reliable technical guarantee for the safe and stable operation of domestic nuclear power plants.