Prediction calculations and experiments for the first criticality of the 10 MW high temperature gas-cooled reactor-test module

Nuclear Engineering and Design

Volumn 218, Issue 1-3, 2002, Pages 43-49

  Jing, Xingqing ^a   Xu, Xiaolin ^a   Yang, Yongwei ^a   Qu, Ronghong ^a  

^a TSINGHUA UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

ERRORS; EXPERIMENTAL REACTORS; EXTRAPOLATION; GRAPHITE; HIGH TEMPERATURE REACTORS; NUCLEAR FUEL ELEMENTS;

REACTOR TEST MODULES;

GAS COOLED REACTORS;

EID: 0036783497     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00184-X     Document Type: Article

References (8)

1. The computer simulation of pebble bed reactor
2. The physics design of HTR-10 test module
3. Features of safety and simplicity of advanced pebble bed HTRs
4. Physics calculation and analysis for HTR-10 initial core and running in phase
5. Scheme study of HTR-10 initial core loaded with homogeneous mixture of spherical graphite and spherical fuel element