Break Size Sensitivity Analysis

Break Size Sensitivity Analysis is a computational evaluation method used in nuclear safety engineering that systematically assesses the response of an Emergency Core Cooling System to a range of postulated pipe break sizes, distinguishing itself by quantifying system performance thresholds and reliability as a function of break severity.

7

Publications

167

Citations

31

Authors

14

Institutions

Publications per year

2017–2026

4

Authors

31

  1. VM
    Victor M. Becerra

    University of Reading, United Kingdom

    1 publications · 25 citations

    1

    h-index

  2. YA
    Yoshinari Anoda

    Japan Atomic Energy Agency, Japan

    1 publications · 12 citations

    1

    h-index

  3. GL
    Gen Li

    Chinese Academy of Sciences, China

    1 publications · 12 citations

    1

    h-index

  4. SM
    Stephen M. Bajorek

    United States Nuclear Regulatory Commission, United States

    1 publications · 55 citations

    1

    h-index

  5. AG
    Ashish Ghosh

    Indian Statistical Institute, India

    1 publications · 28 citations

    1

    h-index

1–5 of 31

Venues

  1. Progress in Nuclear Energy

    3 publications · 58 citations

    3

    h-index

  2. Annals of Nuclear Energy

    2 publications · 42 citations

    2

    h-index

  3. Journal of Nuclear Science and Technology

    JNST · 1 publications · 12 citations

    1

    h-index

  4. Nuclear Engineering and Design

    1 publications · 55 citations

    1

    h-index

1–4