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Nuclear Engineering and Design
Latest Publications
TOTAL DOCUMENTS
16188
(FIVE YEARS 1480)
H-INDEX
99
(FIVE YEARS 11)
Published By Elsevier
0029-5493
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Most Cited Documents
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Latest Documents
Most Cited Documents
Contributed Authors
Related Sources
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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
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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
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Reactor Core
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Implementation and validation of CHF-models in the two-phase porous-media code TWOPORFLOW
Nuclear Engineering and Design
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10.1016/j.nucengdes.2021.111631
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2022
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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
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10.1016/j.nucengdes.2021.111597
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2022
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Vol 389
◽
pp. 111597
Author(s):
Andrea Fregni
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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
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2022
◽
Vol 388
◽
pp. 111627
Author(s):
Tadej Holler
◽
Ed M.J. Komen
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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
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10.1016/j.nucengdes.2021.111644
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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
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10.1016/j.nucengdes.2021.111645
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2022
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Vol 388
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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
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10.1016/j.nucengdes.2021.111613
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2022
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Vol 388
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pp. 111613
Author(s):
Mohamed Mira
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O. El Hajjaji
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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
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10.1016/j.nucengdes.2021.111607
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2022
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Vol 388
◽
pp. 111607
Author(s):
J. Pacio
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S.K. Chen
◽
Y.M. Chen
◽
N.E. Todreas
Keyword(s):
Flow Distribution
◽
Rod Bundles
◽
Detailed Model
◽
Pressure Losses
Download Full-text
Comparing the dynamic response of U-tube and helical coil steam generators in small modular reactor flexible operation
Nuclear Engineering and Design
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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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