核电厂蒸汽发生器传热管氦气检漏系统研究

本研究介绍了某核电厂蒸汽发生器传热管在役氦气检漏系统的原理及系统组成，并模拟了某核电厂蒸汽发生器在役大修期间传热管检漏试验。试验结果表明，最佳参数可设置为:蒸汽发生器二次侧氦气浓度份额为30%；抽气速率为 20 L/min；蒸汽发生器二次侧压力为0.6 MPa；系统漏点定位误差在0.5 m以内。本文研究的蒸汽发生器传热管在役氦气检漏系统可为国内核电厂安全、稳定地运行提供可靠的技术保障。 

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.