Thermal hydraulic transient analysis of the HTR-10

Nuclear Engineering and Design

Volumn 218, Issue 1-3, 2002, Pages 65-80

  Zuying, Gao ^a   Lei, Shi ^a  

^a TSINGHUA UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

CORROSION; FISSION PRODUCTS; GAS COOLED REACTORS; GRAPHITE; NUCLEAR FUEL ELEMENTS; RADIOACTIVITY; TEMPERATURE CONTROL; TRANSIENTS;

GRAPHITE CORROSION;

HIGH TEMPERATURE REACTORS;

EID: 0036784252     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00199-1     Document Type: Article

References (8)

1. Thermal response of a modular HTR under accident conditions
2. Technical design features and safety-related properties of the HTR-module
3. The consequences of water ingress into the primary circuit of an HTR-module - From design basis accident to hypothetical postulates
4. Recriticality of The HTR-module power reactor after hypothetical accidents
5. Meeting fuel temperature limits in an HTR-module reactor during depressurized core heat-up
6. High temperature reactor core physics and reactor dynamics
7. The general design features of 10 MW HTR test module