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Jean-Marie Le Corre
Observed names:
J.-M. Le Corre,
J.M. Le Corre,
Jean-Marie Corre
Institution:
Westinghouse Electric (Sweden)
Observed institutions:
Purdue University West Lafayette,
Westinghouse Electric (Sweden),
Carnegie Mellon University,
KTH Royal Institute of Technology,
Westinghouse Electric (United States)
ORCID:
0000-0002-6013-8074
Observed ORCID:
0000-0002-6013-8074
OpenAlex ID:
A5066477527
Two-phase flow regimes and mechanisms of critical heat flux under subcooled flow boiling conditions
2009
·
Jean-Marie Le Corre
, Shi-Chune Yao
, et al.
·
Nuclear Engineering and Design
·
49
Benchmarking and improvements of measurement techniques for local-time-averaged two-phase flow parameters
2003
·
J.-M. Le Corre
, E. Hervieu
, et al.
·
Experiments in Fluids
·
47
Numerical evaluation and correction method for multi-sensor probe measurement techniques in two-phase bubbly flow
2002
·
Jean-Marie Le Corre
, Mamoru Ishii
·
Nuclear Engineering and Design
·
43
Measurements of local two-phase flow parameters in fuel bundle under BWR operating conditions
2017
·
J.-M. Le Corre
, U.C. Bergmann
, et al.
·
Nuclear Engineering and Design
·
32
Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies
2011
·
Carl Adamsson
, Jean-Marie Le Corre
·
Nuclear Engineering and Design
·
31
Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements
2024
·
G. Bois
, P. Fillion
, et al.
·
International Journal of Multiphase Flow
·
26
A mechanistic model of critical heat flux under subcooled flow boiling conditions for application to one- and three-dimensional computer codes
2009
·
Jean-Marie Le Corre
, Shi-Chune Yao
, et al.
·
Nuclear Engineering and Design
·
25
Phenomenological model of disturbance waves in annular two-phase flow
2022
·
Jean-Marie Le Corre
·
International Journal of Multiphase Flow
·
22
Experimental characterization of boiling two-phase flow structures under BWR core operating conditions
2020
·
J.-M. Le Corre
·
Nuclear Engineering and Design
·
22
A new paradigm for the role of disturbance waves on film dryout and wall heat transfer in annular two-phase flow
2023
·
Roman W. Morse
, Jason Chan
, et al.
·
International Journal of Heat and Mass Transfer
·
21
Transient dryout prediction using a computationally efficient method for sub-channel film-flow analysis
2014
·
C. Adamsson
, J.M. Le Corre
·
Nuclear Engineering and Design
·
17
Investigation of Machine Learning Regression Techniques to Predict Critical Heat Flux Over a Large Parameter Space
2024
·
Emil Helmryd Grosfilley
, Gustav Robertson
, et al.
·
Nuclear Technology
·
15
Wall heat transfer and dryout governed by disturbance wave frequency in annular two-phase flow
2023
·
Roman W. Morse
, Jason Chan
, et al.
·
Experimental Thermal and Fluid Science
·
13
Experimental investigation and modeling of void drift in modern BWR fuel designs
2018
·
J.-M. Le Corre
·
Nuclear Engineering and Design
·
13
Two-phase flow pattern identification using a fuzzy methodology
2003
·
J.-M. Le Corre
, Y. Aldorwish
, et al.
·
IEEE International Conference on Industrial and Information Systems (ICIIS)
·
12
Flow regimes and mechanistic modeling of critical heat flux under subcooled flow boiling conditions
2007
·
Jean-Marie Le Corre
·
9
MEFISTO: A Mechanistic Tool for the Prediction of Critical Power in BWR Fuel Assemblies
2008
·
Carl Adamsson
, Jean-Marie Le Corre
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
·
7
Mechanistic prediction of Westinghouse TRITON11® BWR fuel critical power with MEFISTO-T subchannel analysis code
2024
·
Jean-Marie Le Corre
·
Nuclear Engineering and Design
·
5
Tomographic reconstructions and predictions of radial void distribution in BWR fuel bundle with part-length rods
2015
·
Magnus Ahnesjö
, Peter Andersson
, et al.
·
5
Validation of VIPRE-W sub-channel void predictions using NUPEC/BFBT measurements
2009
·
Karolina Brynjell-Rahkola
, Jean-Marie Le Corre
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
Iterative computed tomography reconstruction of void fraction in a fuel bundle on unstructured mesh
2022
·
Jean-Marie Le Corre
·
Nuclear Engineering and Design
·
3
CFD Modeling of Annular Flow With a Three-Field Approach
2018
·
Salvatore Raddino
, Tobias Strömgren
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
·
3
Validation of VIPRE-W/MEFISTO-T Subchannel Analysis Code for Void Fraction Predictions in Modern BWR Fuel Assemblies
2023
·
Jean-Marie Corre
·
International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH)
·
2
Three-Field subchannel modeling of CANDU fuel thermal-hydraulics with MEFISTO-T code
2025
·
Jean-Marie Le Corre
·
Nuclear Engineering and Design
·
1
Experimental investigation of the internal structure of boiling two-phase water flow under LWR core operating conditions
2025
·
J.-M. Le Corre
, H. Li
, et al.
·
Nuclear Engineering and Design
·
1
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Works count:
34
Citation count:
431
H-index:
13
I10-index:
15
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