Thermal-hydraulic Codes
Thermal-Hydraulic Codes is a computational framework consisting of numerical models and algorithms designed to simulate the behavior of fluid flow, heat transfer, and associated phenomena in nuclear reactor systems under normal, transient, and accident conditions, distinguishing it from general-purpose fluid dynamics tools by its specialized application to nuclear thermal-hydraulic safety analysis.
709
Publications
36.3K
Citations
2.1K
Authors
386
Institutions
Publications per year
2017–2026
224
Variants
Thermal-hydraulic System Codes
709
Numerical Heat Transfer and Fluid Flow
Chia‐Jung Hsu · Nuclear Science and Engineering · 1981 · 15.2K citations
Engineering, Mechanical Engineering, Nuclear Engineering +17
The ASME boiler and pressure vessel code
J.W. Stokes, L. Holly, Karl-Heinz Mayer · Non-Destructive Testing · 1974 · 380 citations
Engineering, Mechanical Engineering, Systems Engineering +14
1–5 of 709
2.1K
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Karlsruhe Institute of Technology, Germany
16 publications · 376 citations
13
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1–5 of 2.1K
386
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
Paris, France
24 h-index
95 publications
4.7K citations

Xi'an Jiaotong University
Xi'an, China
21 h-index
251 publications
7K citations

University of Pisa
Pisa, Italy
21 h-index
119 publications
2.9K citations
Korea Atomic Energy Research Institute
Daejeon, South Korea
21 h-index
137 publications
3.8K citations
Karlsruhe Institute of Technology
Karlsruhe, Germany
19 h-index
104 publications
2.5K citations
Gesellschaft für Anlagen und Reaktorsicherheit
Cologne, Germany
16 h-index
38 publications
1.2K citations

Idaho National Laboratory
Idaho Falls, United States
16 h-index
52 publications
2.1K citations

Helmholtz-Zentrum Dresden-Rossendorf
Dresden, Germany
15 h-index
60 publications
1.8K citations
1–8 of 386
161 publications · 4.9K citations
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99 publications · 2.7K citations
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66 publications · 1.8K citations
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27 publications · 16.3K citations
19
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29 publications · 722 citations
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