Theoretical study in single-phase forced-convection heat transfer characteristics for narrow annuli fuel coolant channels

Periodica Polytechnica Mechanical Engineering

Volumn 46, Issue 1, 2002, Pages 15-27

  Bsebsu, F M ^a   Bede, G ^a  

^a BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS   (Hungary)

Author keywords

Heat transfer correlation; Reactor heat transfer; Reactor safety; Research reactor; Thermal hydraulics; WWR M2 channel

Indexed keywords

COMPUTER SIMULATION; COOLANTS; CORRELATION METHODS; FRICTION; HEAT FLUX; HEAT TRANSFER COEFFICIENTS; HYDRAULICS; NUSSELT NUMBER; PRANDTL NUMBER; RESEARCH REACTORS; REYNOLDS NUMBER; SPECIFIC HEAT; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY; TURBULENT FLOW; WATER COOLED REACTORS;

THERMAL HYDRAULICS;

FORCED CONVECTION;

EID: 0036264099     PISSN: 03246051     EISSN: 1587379X     Source Type: Journal    
DOI: None     Document Type: Article

References (13)

1. Thin-walled fuel elements WWR-M2 for research reactors
2. Remarks to the reconstruction of active zone in the nuclear reactor type WWR-M2
3. Design and experience of HEU and LEU fuel for WWR-M2 reactors
4. Nuclear reactor channel modelling using the THMOD2 code
5. Tajoura reactor power uprating - Thermal hydraulic analysis
6. Experimental study of differences in single-phase forced-convection heat transfer characteristics between up-flow and downflow for narrow rectangular channel