Experimental measurements of fluid flow in an 84-pin hexagonal rod bundle with spacer grid for a gas-cooled fast modular reactor

Direct numerical simulation of fluid flow in a 5x5 square rod bundle

(2021) Adam Kraus et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Experimental investigation of turbulent wake flows in a helically wrapped rod bundle in presence of localized blockages

(2020) T. Nguyen et al.   PHYSICS OF FLUIDS

Experimental measurements of turbulent flows in a rod bundle with a 3-D printed channel-type spacer grid

(2020) Camila F. Matozinhos et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Experimental investigation of turbulent flow characteristics in cross-flow planes of a 5×5 rod bundle with a spacer grid

(2020) Camila F. Matozinhos et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Experimental investigation of cross flow mixing in a randomly packed bed and streamwise vortex characteristics using particle image velocimetry and proper orthogonal decomposition analysis

(2019) T. Nguyen et al.   PHYSICS OF FLUIDS

Invariant analysis of the Reynolds stress tensor for a nuclear fuel assembly with spacer grid and split type vanes

(2019) Giacomo Busco et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Experimental investigation on the influence of gap vortex streets on fluid-structure interactions in hexagonal bundle geometries

(2019) F. Bertocchi et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Stereoscopic PIV measurements of near-wall flow in a tightly packed rod bundle with wire spacers

(2018) Thien Nguyen et al.   EXPERIMENTAL THERMAL AND FLUID SCIENCE

Time-resolved PIV measurements in a low-aspect ratio facility of randomly packed spheres and flow analysis using modal decomposition

(2018) Thien Nguyen et al.   EXPERIMENTS IN FLUIDS

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

Space and energy-based turbulent scale-resolving simulations of flow in a 5 × 5 nuclear reactor core fuel assembly with a spacer grid

(2018) Giacomo Busco et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Convergence study and uncertainty quantification of average and statistical PIV measurements in a matched refractive index 5×5 rod bundle with mixing vane spacer grid

(2018) André Augusto Campagnole dos Santos et al.   EXPERIMENTAL THERMAL AND FLUID SCIENCE

Automated mask generation for PIV image analysis based on pixel intensity statistics

(2017) Alessandro Masullo et al.   EXPERIMENTS IN FLUIDS

Stereoscopic particle image velocimetry measurements of flow in a rod bundle with a spacer grid and mixing vanes at a low Reynolds number

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

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

Perspectives on CFD analysis in nuclear reactor regulation

(2016) Christopher Boyd   NUCLEAR ENGINEERING AND DESIGN

Prediction of CRUD deposition on PWR fuel using a state-of-the-art CFD-based multi-physics computational tool

(2016) Victor Petrov et al.   NUCLEAR ENGINEERING AND DESIGN

Benchmark exercise for fluid flow simulations in a liquid metal fast reactor fuel assembly

(2016) E. Merzari et al.   NUCLEAR ENGINEERING AND DESIGN

LES analysis of the flow in a simplified PWR assembly with mixing grid

(2014) Ulrich Bieder et al.   PROGRESS IN NUCLEAR ENERGY

Thermal-hydraulic study of a wire spacer fuel assembly

(2011) Stefano Rolfo et al.   NUCLEAR ENGINEERING AND DESIGN

Assessment of advanced windowing techniques for digital particle image velocimetry (DPIV)

(2009) Adric Eckstein et al.   MEASUREMENT SCIENCE and TECHNOLOGY

Digital particle image velocimetry (DPIV) robust phase correlation

(2009) Adric Eckstein et al.   MEASUREMENT SCIENCE and TECHNOLOGY

Flow visualization in a pebble bed reactor experiment using PIV and refractive index matching techniques

(2008) Yassin A. Hassan et al.   NUCLEAR ENGINEERING AND DESIGN