General design of the 10 MW HTR

According to the development programme of advanced technologies in China, a 10 MW side-by-side high temperature gas-cooled test module reactor with spherical fuel elements will be erected before the year 2000 by the Institute of Nuclear Energy Technology of Tsinghua University. The aims of this project are to demonstrate the inherent safety features of the HTGR modular design and to test the technologies of electricity generation, district heating as well as process heat application with modular HTGR. At present, the 10 MW HTR main building is being constructed and the principle large components have been ordered and are being fabricated. The design philosophy and safety features, the reactor structure, the principle components, the design parameters, the general layout of principle systems in the nuclear island of the 10 MW high temperature gas-cooled test module are described. (J.P.N.)