Investigation of pressure loss and velocity distribution in fuel assemblies with wire-wrapped rods by using RANS and LES with wall functions

CFD analysis of intra and inter fuel assembly mixing

(2019) Ulrich Bieder et al.   ANNALS OF NUCLEAR ENERGY

Validating RANS to predict the flow behavior in wire-wrapped fuel assemblies

(2019) Daniele Dovizio et al.   NUCLEAR ENGINEERING AND DESIGN

Analysis of the IAEA benchmark on heat transfer in a 4 × 4 rod bundle with mixing grid

(2018) Ulrich Bieder et al.   ANNALS OF NUCLEAR ENERGY

PTV/PIV measurements of turbulent flows in interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle

(2018) Nolan Goth et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Comparison of experimental and simulation results on interior subchannels of a 61-pin wire-wrapped hexagonal fuel bundle

(2018) N. Goth et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor

(2018) Min Seop Song et al.   Nuclear Engineering and Technology

Assessment of RANS models for flow in a loosely spaced bare rod bundle with heat transfer in low Prandtl number fluid

(2018) B. Mikuž et al.   ANNALS OF NUCLEAR ENERGY

PIV measurements of turbulent flows in a 61-pin wire-wrapped hexagonal fuel bundle

(2017) Thien Nguyen et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Pressure Measurements in a Wire-Wrapped 61-Pin Hexagonal Fuel Bundle

(2017) Rodolfo Vaghetto et al.   JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME

RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR

(2017) Jae-Ho Jeong et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region

(2013) S.K. Chen et al.   NUCLEAR ENGINEERING AND DESIGN

A comparative CFD investigation of helical wire-wrapped 7, 19 and 37 fuel pin bundles and its extendibility to 217 pin bundle

(2009) R. Gajapathy et al.   NUCLEAR ENGINEERING AND DESIGN

Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations

(2008) E. Bubelis et al.   NUCLEAR ENGINEERING AND DESIGN

Effects of wire-spacer shape in LMR on thermal–hydraulic performance

(2008) Wasim Raza et al.   NUCLEAR ENGINEERING AND DESIGN