Multi-group Cross Section Generation

Multi-Group Cross Section Generation is a computational methodology in nuclear reactor physics that, as a subset of homogenization methods, reduces continuous energy-dependent neutron cross sections into a discrete set of energy-averaged values over predefined energy groups to enable efficient neutronic diffusion and transport calculations.

27

Publications

709

Citations

82

Authors

31

Institutions

Publications per year

2017–2026

17

Authors

82

  1. WS
    Won Sik Yang

    Argonne National Laboratory, United States

    4 publications · 154 citations

    4

    h-index

  2. KS
    Kang Seog Kim

    Oak Ridge National Laboratory, United States

    3 publications · 58 citations

    3

    h-index

  3. BT
    B.J. Toppel

    Argonne National Laboratory, United States

    2 publications · 139 citations

    2

    h-index

  4. HG
    Hui Guo

    Shanghai Jiao Tong University, China

    2 publications · 27 citations

    2

    h-index

  5. KT
    Kenichi Tada

    Japan Atomic Energy Agency, Japan

    2 publications · 33 citations

    2

    h-index

1–5 of 82

Venues

  1. Annals of Nuclear Energy

    6 publications · 117 citations

    6

    h-index

  2. Nuclear Science and Engineering

    6 publications · 201 citations

    6

    h-index

  3. Nuclear Engineering and Technology

    5 publications · 98 citations

    5

    h-index

  4. Journal of Nuclear Science and Technology

    JNST · 2 publications · 33 citations

    2

    h-index

  5. Nuclear Technology

    1 publications · 56 citations

    1

    h-index

1–5