Pellet-cladding Interaction

Pellet-Cladding Interaction is a mechanical degradation phenomenon in nuclear fuel rods characterized by stress-induced deformation and potential failure at the interface between uranium dioxide fuel pellets and the surrounding zirconium-based cladding, driven by thermal expansion, irradiation-induced swelling, and fission gas pressure during reactor operation.

71

Publications

1.6K

Citations

220

Authors

59

Institutions

Publications per year

2017–2026

16

Authors

220

  1. TF
    Toyoshi FUKETA

    Japan Atomic Energy Agency, Japan

    6 publications · 170 citations

    6

    h-index

  2. TS
    Tomoyuki Sugiyama

    Japan Atomic Energy Agency, Japan

    6 publications · 114 citations

    6

    h-index

  3. JS
    J. Sercombe

    Commissariat à l'Énergie Atomique et aux Énergies Alternatives, France

    6 publications · 247 citations

    6

    h-index

  4. FN
    Fumihisa Nagase

    Japan Atomic Energy Agency, Japan

    4 publications · 80 citations

    4

    h-index

  5. SL
    Sanghoon Lee

    Seoul National University, South Korea

    3 publications · 51 citations

    3

    h-index

1–5 of 220

Venues

  1. Nuclear Engineering and Design

    19 publications · 364 citations

    13

    h-index

  2. Journal of Nuclear Science and Technology

    JNST · 13 publications · 294 citations

    12

    h-index

  3. Journal of Nuclear Materials

    7 publications · 168 citations

    8

    h-index

  4. Nuclear Technology

    7 publications · 207 citations

    7

    h-index

  5. Nuclear Engineering and Technology

    4 publications · 56 citations

    4

    h-index

1–5