Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle

Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle

(2021) Mason Childs et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles

(2021) Octavio Bovati et al.   INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW

Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor

(2021) Qi Zhang et al.   ANNALS OF NUCLEAR ENERGY

Numerical simulation of the thermal-hydraulic characteristics of supercritical carbon dioxide in a wire-wrapped rod bundle

(2021) Shunqi Wang et al.   APPLIED THERMAL ENGINEERING

CFD investigation for a 7-pin wire-wrapped fuel assembly with different shapes of fuel duct wall

(2020) Yuanyuan Zhao et al.   ANNALS OF NUCLEAR ENERGY

An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle

(2020) Yu Liang et al.   APPLIED THERMAL ENGINEERING

Thermal-hydraulic analysis of a 7-pin sodium-cooled fast reactor wire-wrapped fuel bundle

(2020) Dianle Wang et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics

(2020) Minseop Song et al.   NUCLEAR ENGINEERING AND DESIGN

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

(2020) U. Bieder et al.   ANNALS OF NUCLEAR ENERGY

CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle

(2019) Xiang Chai et al.   NUCLEAR ENGINEERING AND DESIGN

Thermal-Hydraulic Experimental Testing of the Myrrha Wire-Wrapped Fuel Assembly

(2019) Graham Kennedy et al.   NUCLEAR TECHNOLOGY

Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus

(2019) Hao Qin et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

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

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

Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer

(2018) Seong Dae Park et al.   ANNALS OF NUCLEAR ENERGY

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

Analysis of inter-channel sweeping flow in wire wrapped 19-rod bundle

(2018) Xi Wang et al.   NUCLEAR ENGINEERING AND DESIGN

The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles

(2018) S.K. Chen et al.   NUCLEAR ENGINEERING AND DESIGN

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

Experimental investigation on boiling heat transfer of high pressure water in a SCWR sub-channel

(2017) Han Wang et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Experimental study on transient heat transfer across critical pressure in 2 × 2 rod bundle with wire wraps

(2017) Hong-bo Li et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR

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

CFD analysis of transverse flow in a wire-wrapped hexagonal seven-pin bundle

(2017) Pinghui Zhao et al.   NUCLEAR ENGINEERING AND DESIGN

Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor

(2016) M. Naveen Raj et al.   ANNALS OF NUCLEAR ENERGY

Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactor

(2016) Hyungmo Kim et al.   ANNALS OF NUCLEAR ENERGY

Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water

(2016) Han Wang et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel bundle for SFR

(2015) Jae-Ho Jeong et al.   Nuclear Engineering and Technology

Single-phase cross-mixing measurements in a 4×4 rod bundle

(2011) Arto Ylönen et al.   NUCLEAR ENGINEERING AND DESIGN

Effect of density-driven flow on the through-diffusion experiment

(2009) Yusuke Kirino et al.   JOURNAL OF CONTAMINANT HYDROLOGY