Numerical simulation research on the spiral tube of high temperature gas-cooled reactor steam generator

As the fourth generation nuclear power reactor, the miniaturization, modular design concept and the technical advantages of inherent safety characteristics of High Temperature Gas-cooled Reactor have been paid more and more attention. The complex flow and thermal hydraulic characteristics in helical steam generator have been studied by numerical simulation. The design parameters of the helical steam generator of the 10 MW High Temperature Gas-cooled Reactor built by Tsinghua University Institute of nuclear energy technology have been applied. The numerical results are compared with the experimental results. The outlet temperature errors of numerical method of are less than 30 ℃, while the pressure drop errors of numerical results are less than 5%. (authors)