Overview of the 10 MW high temperature gas cooled reactor - Test module project

Nuclear Engineering and Design

Volumn 218, Issue 1-3, 2002, Pages 13-23

  Xu, Yuanhui ^a   Zuo, Kaifen ^a  

^a TSINGHUA UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

GRAPHITE; HIGH TEMPERATURE REACTORS; REACTOR CORES; SAFETY FACTOR;

HIGH TEMPERATURE GAS COOLED REACTORS (HTGR);

GAS COOLED REACTORS;

EID: 0036783501     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00181-4     Document Type: Article

References (8)

1. Technical design features and essential safety-related properties of the HTR-module
2. Status of design of the HTR test module China
3. Licensing of the HTR-10 test reactor
4. High temperature engineering research facilities and experiments in China
5. Study on modular high temperature gas-cooled reactor and its application for heavy oil recovery 1985.11