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

Authors

2.1K

  1. SQ
    Suizheng Qiu

    Xi'an Jiaotong University, China

    35 publications · 1.1K citations

    18

    h-index

  2. WT
    Wenxi Tian

    Xi'an Jiaotong University, China

    31 publications · 887 citations

    17

    h-index

  3. GS
    G.H. Su

    Xi'an Jiaotong University, China

    28 publications · 876 citations

    16

    h-index

  4. FS
    Francesco Saverio D'Auria

    University of Pisa, Italy

    24 publications · 765 citations

    16

    h-index

  5. VH
    Víctor Hugo Sánchez-Espinoza

    Karlsruhe Institute of Technology, Germany

    16 publications · 376 citations

    13

    h-index

1–5 of 2.1K

Venues

  1. Nuclear Engineering and Design

    161 publications · 4.9K citations

    38

    h-index

  2. Annals of Nuclear Energy

    99 publications · 2.7K citations

    28

    h-index

  3. Nuclear Technology

    66 publications · 1.8K citations

    22

    h-index

  4. Nuclear Science and Engineering

    27 publications · 16.3K citations

    19

    h-index

  5. Nuclear Engineering and Technology

    29 publications · 722 citations

    18

    h-index

1–5