Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod 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

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

Design concepts of supercritical water-cooled reactor (SCWR) and nuclear marine vessel: A review

(2020) Mohammad Mizanur Rahman et al.   PROGRESS IN NUCLEAR ENERGY

Experimental Study on the Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle

(2020) Mason Childs et al.   JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME

CFD and thermal-hydraulics analyses of liquid sodium heat transfer in 19-rod hexagonal bundles with scalloped walls

(2019) Luis M. Palomino et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

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

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

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

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

Numerical simulations for determination of minimum representative bundle size in wire wrapped tube bundles

(2017) Landon Brockmeyer et al.   NUCLEAR ENGINEERING AND DESIGN

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

Experimental study of heavy-liquid metal (LBE) flow and heat transfer along a hexagonal 19-rod bundle with wire spacers

(2016) J. Pacio et al.   NUCLEAR ENGINEERING AND DESIGN

Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor

(2016) Seok-Kyu Chang et al.   Nuclear Engineering and Technology

Review of R&D for supercritical water cooled reactors

(2014) Thomas Schulenberg et al.   PROGRESS IN NUCLEAR ENERGY

Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles

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

Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method

(2012) Syeilendra Pramuditya et al.   ANNALS OF NUCLEAR ENERGY

Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow

(2011) A. Chenu et al.   NUCLEAR ENGINEERING AND DESIGN

The thermal hydraulics in a rod bundle representative of the start-up core of the ALLEGRO Gas cooled Fast Reactor—Experimental and numerical approaches

(2010) Marc Berthoux 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