Study on two phases flow flow-induced vibration of nuclear pressure retaining heat exchanger

In order to ensure the safety of nuclear pressure retaining heat exchanger, the analysis for two phases flow flow-induced vibration of nuclear pressure retaining heat exchanger and control measures was presented by using computational fluid dynamics (CFD) and software calculation method. The results show that based on the theory of flow-induced vibration, crossflow velocity, natural frequency, vortex shedding frequency and turbulent buffeting frequency should be the key factors. Based on the formula, flow rate, tube diameter, tube wall thickness and pipe bundles layout have direct effects on flow-induced vibration, Unsupported tube span is the biggest factor influence flow-induced vibration. The most serious area of flow-induced vibration exists in inlet area, outlet area, baffle cut area and large unsupported tube span area. In the design, flow rate, tube diameter, tube wall thickness, unsupported tube span, pipe bundles layout and impingement baffle should be optimized, to reduce risk of flow-induced vibration. (authors)