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Tsinghua 04790004 (8389261478).jpg
Control room of HTR-10 reactor
CountryPeople's Republic of China
CoordinatesCoordinates: 40°15′26″N 116°08′59″E / 40.257169°N 116.149758°E / 40.257169; 116.149758
Construction began1995
Commission dateJanuary 2003
Owner(s)Tsinghua University
Nuclear power station
Reactor typepebble-bed reactor HTGR
Cooling source
Power generation
Units operational10 MW

HTR-10 is a 10 MWt prototype pebble bed reactor at Tsinghua University in China. Construction began in 1995, achieving its first criticality in December 2000, and was operated in full power condition in January 2003.[1]

Two HTR-PM reactors, scaled up versions of the HTR-10 with 250-MWt capacity, were installed at the Shidao Bay Nuclear Power Plant near the city of Rongcheng in Shandong Province and achieved first criticality in september 2021.


HTR-10 is modeled after the German HTR-MODUL. Like the HTR-MODUL, HTR-10 is claimed to be fundamentally safer,[2] potentially cheaper and more efficient than other nuclear reactor designs.[citation needed] Outlet temperature ranges between 700 and 950 °C (1,300–1,750 °F), which allows these reactors to generate hydrogen as a byproduct efficiently, thus supplying inexpensive and non-polluting fuel for fuel cell powered vehicles.[3]

HTR-10 is a pebble-bed reactor HTGR utilizing spherical fuel elements with ceramic coated fuel particles. The reactor core has a diameter of 1.8 m, a mean height of 1.97 m and the volume of 5.0 m³, and is surrounded by graphite reflectors. The core is composed of 27,000 fuel elements. The fuel elements use low enriched uranium with a design mean burn up of 80,000 MWd/t. The pressure of the primary helium coolant circuit is 3.0 Mpa.[4]

See also[edit]


  1. ^ HTR-10, 2010, retrieved 2013-02-25
  2. ^ Hu, Shouyin; Wang, Ruipian; Gao, Zuying (2004), "Safety Demonstration Tests On HTR-10", Proceedings of the Conference on High Temperature Reactors, Beijing, China: 1–16, archived from the original on 2011-07-25, retrieved 2010-04-26
  3. ^ Sun, Yuliang; Xu, Jingming; Zhang, Zuoyi (2006), "R&D effort on nuclear hydrogen production technology in China", International Journal of Nuclear Hydrogen Production and Applications, 1 (2): 104–111, doi:10.1504/ijnhpa.2006.011245, archived from the original on 2013-01-28, retrieved 2010-04-26
  4. ^ "The High Temperature Gas Cooled Reactor Test Module Core Physics Benchmarks; from google (htr-10 fuel) result 3" (PDF).

External links[edit]