An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies

Annals of Nuclear Energy

Volumn 28, Issue 17, 2001, Pages 1683-1695

  Chun, Moon Hyun ^a   Seo, Kyong Won ^a  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

Pressure drop correlations; Subchannel analysis; Wire wrapped rod bundle

Indexed keywords

FRICTION; PRESSURE DROP; TURBULENT FLOW;

PRESSURE DROP CORRELATIONS; WIRE WRAPPED ROD BUNDLES;

NUCLEAR FUELS;

EID: 0035501959     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(01)00023-8     Document Type: Article

References (7)

1. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-bundle friction factors, subchannel friction factors and mixing parameters
2. Laminar, transition, and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles
3. MATRA-LMR code for thermal-hydraulic subchannel analysis of LMR
4. Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system
5. Pressure drop correlations for fuel element spacers
6. Development of subchannel analysis code MATRA α-version