Research method and two-phase flow stability of the steam generator of HTR-10

A 10 MW High Temperature Gas Cooled Reactor (HTR-10) designed by the Instit ute of Nuclear Energy Technology (INET) of Tsinghua University is being con structed now. The steam generator (SG) of the HTR-10 is one of the most imp ortant facilities for reactor safety, In order to investigate the thermal-h ydraulic performance of the SG, a full scale HTR-10 Steam Generator Two Tub e Engineering Model Test Facility (SGTM-10) was installed and tested at INE T. This paper describes the SGTM-10 in detail. The test assembly of the SGT M-10 simulates practical thermal and structural parameters of the HTR-10. T he SGTM-10 consisted of three separated loops, primary-helium loop, seconda ry-water loop, and third-cooling water loop. There are two parallel tubes a rranged in the test assembly. The main experimental equipment is shown in t his paper, Analysis shows that for once-through steam generator simulation experiment, the electric-heated simulation method could not match practical operating condition. The results may not reflect true phenomena. The main results of experiments, for example effects of the outlet pressure, effects of the heating power, effects of the inlet sub-cooling are described. Expe riments indicated, when the heat load of the HTR-10 is more than 30% the SG will be stable.