Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core

Nuclear Engineering and Design

Volumn 218, Issue 1-3, 2002, Pages 51-64

  Gao, Zuying ^a   Shi, Lei ^a  

^a TSINGHUA UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTATIONAL METHODS; FLOW MEASUREMENT; GAS COOLED REACTORS; GRAPHITE; NUCLEAR FUEL ELEMENTS; REACTOR CORES; TEMPERATURE DISTRIBUTION;

EQUILIBRIUM CORES;

HIGH TEMPERATURE REACTORS;

EID: 0036783867     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00198-X     Document Type: Article

References (6)

1. Simulation tests for temperature mixing in a core bottom model of the HTR-Module
2. Thermal response of a modular HTR under accident conditions
3. Steady thermohydraulic analysis of 10 MW HTGR
4. Technical design features and safety-related properties of the HTR-module
5. High temperature reactor core physics and reactor dynamics