The design features of the HTR-10

By Zongxin Wu, Dengcai Lin, Daxin Zhong. 2002

384 citations recorded by the source corpus.

Subfields: Aerospace Engineering, Materials Chemistry

View Paper: https://www.semanticscholar.org/paper/ad565fc76141d5cfa4a4247af40dc8a000ccc69f

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In Materials Chemistry

1. Hong Wang

Citations in the corpus

• The Shandong Shidao Bay 200 MW e High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation (2016, background): “In China, the R&D program for the high-temperature gas-cooled reactor (HTGR) of the Institute of Nuclear and New Energy Technology (INET) at Tsinghua University began in the mid-1970s, and accomplished the construction of the HTR-10 test reactor in the 1990s [4].”
• Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM (2006, neutral): “Supported by the Chinese national hightechnology program, the 10 MW high-temperature gas-cooled test reactor (HTR-10) (Wu et al., 2002), whose design began in 1992 and construction commenced in 1995, reached its criticality in December 2000, and its full power operation in January 2003.”