Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data

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

CFD Verification and Validation of Wire-Wrapped Pin Assemblies

(2020) Mathieu Martin et al.   NUCLEAR TECHNOLOGY

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

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

Adventures in study of the pressure losses in wire-wrapped rod bundle arrays

(2020) Neil Todreas et al.   NUCLEAR ENGINEERING AND DESIGN

A note on the accuracy of the upgraded Cheng and Todreas correlation for predicting pressure drop in hexagonal bare rod bundles

(2019) S.K. Chen et al.   APPLIED THERMAL ENGINEERING

Towards validated prediction with RANS CFD of flow and heat transport in a wire-wrap fuel assembly

(2019) Ferry Roelofs et al.   NUCLEAR ENGINEERING AND DESIGN

Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assembly

(2019) Yeong Shin Jeong 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

Heat transfer experiment in a partially (internally) blocked 19-rod bundle with wire spacers cooled by LBE

(2018) J. Pacio 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

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

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

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

Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic

(2016) Kefeng Lyu et al.   ANNALS OF NUCLEAR ENERGY

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

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

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

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