Overview of 10 MW High Temperature Gas-cooled Reactor-Test Module

The objective, design, construction and commissioning of 10 MW High Temperature Gas-cooled Reactor-Test Module (termed an HTR-10) is one of key project in the National High Technology Research and Development Program(1986-2000). Main objectives for the HTR-10 are to acquire know-how to design, construct and operate the HTGRs, to establish an experimental facility, to demonstrate the inherent safety features of the Modular HTGR, to test electricity and heat co-generation and closed cycle gas turbine technology and to do research and development work for high temperature process heat application. The Institute of Nuclear Energy Technology (INET) of Tsinghua University was appointed as the leading institute to be responsible for design, license applications, construction and operation of the HTR-10. The HTR-10 technical design represents the features of Modular HTGR design. The HTR-10 is a pebble bed high temperature gas-cooled reactor; it uses the spherical fuel elements. The reactor core and the steam generator are housed in two steel pressure vessels, which are arranged side by side. These two vessels are connected to each other by the vessel of the hot gas duct. These three vessels consist of primary pressure boundary. All these steel pressure vessels are in touch with the cold helium of about 250 .deg. C coming out from the circulator, which sits the top of the steam generator vessel