Nuclear Engineering and Design
Latest Publications

TOTAL DOCUMENTS

16188

(FIVE YEARS 1043)

H-INDEX

(FIVE YEARS 4)

Published By Elsevier

0029-5493

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

Experimental investigation on effective thermal conductivity of powder-packed assembly gaps in heat pipe cooled reactor core

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111611 ◽

2022 ◽

Vol 388 ◽

pp. 111611

Author(s):

Li Tao ◽

Du Zhengyu ◽

He Hui ◽

He Xiaoqiang ◽

Qu Wenhai ◽

...

Keyword(s):

Thermal Conductivity ◽

Experimental Investigation ◽

Heat Pipe ◽

Effective Thermal Conductivity ◽

Reactor Core

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Implementation and validation of CHF-models in the two-phase porous-media code TWOPORFLOW

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111631 ◽

2022 ◽

Vol 388 ◽

pp. 111631

Author(s):

Veronica Jauregui Chavez ◽

Uwe Imke ◽

Victor Hugo Sanchez-Espinoza

Keyword(s):

Porous Media ◽

Two Phase

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Direct Numerical Simulation of natural, mixed and forced convection in liquid metals: selected results

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111597 ◽

2022 ◽

Vol 389 ◽

pp. 111597

Author(s):

Andrea Fregni ◽

Diego Angeli ◽

Andrea Cimarelli ◽

Enrico Stalio

Keyword(s):

Numerical Simulation ◽

Direct Numerical Simulation ◽

Forced Convection ◽

Liquid Metals

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The role of CFD combustion modelling in hydrogen safety management – VIII: Use of Eddy Break-Up combustion models for simulation of large-scale hydrogen deflagration experiments

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111627 ◽

2022 ◽

Vol 388 ◽

pp. 111627

Author(s):

Tadej Holler ◽

Ed M.J. Komen ◽

Ivo Kljenak

Keyword(s):

Large Scale ◽

Safety Management ◽

Combustion Models ◽

Combustion Modelling ◽

Break Up ◽

Hydrogen Safety

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Large-eddy simulation on thermal-mixing experiment at horizontal T-junction with varied flow temperature

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111644 ◽

2022 ◽

Vol 388 ◽

pp. 111644

Author(s):

Mi Zhou ◽

Fabian Wiltschko ◽

Rudi Kulenovic ◽

Eckart Laurien

Keyword(s):

Large Eddy Simulation ◽

Flow Temperature ◽

Thermal Mixing ◽

Eddy Simulation ◽

Large Eddy

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Experimental study of interfacial area of bubble plume based on bubble tracking by wire-mesh sensor

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111645 ◽

2022 ◽

Vol 388 ◽

pp. 111645

Author(s):

Kohei Yoshida ◽

Kota Fujiwara ◽

Yuki Nakamura ◽

Akiko Kaneko ◽

Yutaka Abe

Keyword(s):

Experimental Study ◽

Interfacial Area ◽

Wire Mesh ◽

Bubble Plume

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Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111629 ◽

2022 ◽

Vol 388 ◽

pp. 111629

Author(s):

Asiya Rummana ◽

Roger John Barlow ◽

Syed Mohammad Saad

Keyword(s):

Conversion Rates

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Derivation of optimal process MOC parameters and analysis of the 2D C5G7 MOX benchmark using DRAGON5 code

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111613 ◽

2022 ◽

Vol 388 ◽

pp. 111613

Author(s):

Mohamed Mira ◽

O. El Hajjaji ◽

O. Jai ◽

T. El Bardouni ◽

Jamal Al Zain ◽

...

Keyword(s):

Optimal Process

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Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111607 ◽

2022 ◽

Vol 388 ◽

pp. 111607

Author(s):

J. Pacio ◽

S.K. Chen ◽

Y.M. Chen ◽

N.E. Todreas

Keyword(s):

Flow Distribution ◽

Rod Bundles ◽

Detailed Model ◽

Pressure Losses

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Comparing the dynamic response of U-tube and helical coil steam generators in small modular reactor flexible operation

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2021.111610 ◽

2022 ◽

Vol 388 ◽

pp. 111610

Author(s):

Adeel Sabir ◽

Jin Jiang

Keyword(s):

Dynamic Response ◽

Helical Coil ◽

Steam Generators ◽

Small Modular Reactor ◽

Flexible Operation

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Nuclear Engineering and DesignLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By Elsevier

Experimental investigation on effective thermal conductivity of powder-packed assembly gaps in heat pipe cooled reactor core

Implementation and validation of CHF-models in the two-phase porous-media code TWOPORFLOW

Direct Numerical Simulation of natural, mixed and forced convection in liquid metals: selected results

The role of CFD combustion modelling in hydrogen safety management – VIII: Use of Eddy Break-Up combustion models for simulation of large-scale hydrogen deflagration experiments

Large-eddy simulation on thermal-mixing experiment at horizontal T-junction with varied flow temperature

Experimental study of interfacial area of bubble plume based on bubble tracking by wire-mesh sensor

Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX

Derivation of optimal process MOC parameters and analysis of the 2D C5G7 MOX benchmark using DRAGON5 code

Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)

Comparing the dynamic response of U-tube and helical coil steam generators in small modular reactor flexible operation

Nuclear Engineering and Design
Latest Publications