Concepedia

Core Safety Margin Analysis

Core Safety Margin Analysis is a systematic engineering assessment methodology used in reactor core design to quantify the operational and safety margins between prescribed core performance parameters and their regulatory or physical failure limits under postulated transient and accident conditions.

16

Publications

578

Citations

67

Authors

21

Institutions

Publications per year

2017–2026

2

Parents

Publications

16

Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

B.E. Boyack, I. Catton, Romney B. Duffey et al. · Nuclear Engineering and Design · 1990 · 207 citations · Full text

, , +16

Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis

Nicholas R. Brown, Benjamin R. Betzler, J.J. Carbajo et al. · Annals of Nuclear Energy · 2017 · 54 citations · Full text

, , +15

Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs

Ji-Han Chun, Sung-Won Lim, Bub-Dong Chung et al. · Nuclear Engineering and Design · 2015 · 48 citations · Full text

, , +16

Full core LOCA safety analysis for a PWR containing high burnup fuel

Nathan Capps, Aaron Wysocki, Andrew Godfrey et al. · Nuclear Engineering and Design · 2021 · 48 citations · Full text

, , +13

Quantifying reactor safety margins Part 5: Evaluation of scale-up capabilities of best estimate codes

N. Zuber, G.E. Wilson, B.E. Boyack et al. · Nuclear Engineering and Design · 1990 · 36 citations

, , +15

1–5 of 16

Authors

67

  1. GW
    G.E. Wilson

    Idaho National Laboratory, United States

    3 publications · 266 citations

    3

    h-index

  2. KK
    K.R. Katsma

    Idaho National Laboratory, United States

    3 publications · 266 citations

    3

    h-index

  3. NZ
    N. Zuber

    United States Nuclear Regulatory Commission, United States

    3 publications · 266 citations

    3

    h-index

  4. BB
    B.E. Boyack

    Idaho National Laboratory, United States

    3 publications · 266 citations

    3

    h-index

  5. GL
    G.S. Lellouche

    Campbell Soup (United States), United States

    3 publications · 266 citations

    3

    h-index

1–5 of 67

Institutions

21

  1. Oak Ridge National Laboratory

    Oak Ridge, United States

    2 h-index

    12 publications

    618 citations

  2. Idaho National Laboratory

    Idaho Falls, United States

    2 h-index

    3 publications

    82 citations

  3. Pennsylvania State University

    State College, United States

    2 h-index

    2 publications

    68 citations

  4. Indira Gandhi Centre for Atomic Research

    Kālpākkam, India

    2 h-index

    8 publications

    128 citations

  5. Argonne National Laboratory

    Lemont, United States

    2 h-index

    5 publications

    87 citations

  6. National Centre for Nuclear Energy, Science and Technology

    Rabat, Morocco

    1 h-index

    4 publications

    52 citations

  7. Ricardo AEA (United Kingdom)

    London, United Kingdom

    1 h-index

    1 publications

    27 citations

  8. United States Nuclear Regulatory Commission

    Rockville, United States

    1 h-index

    1 publications

    36 citations

1–8 of 21

Venues

  1. Nuclear Engineering and Design

    7 publications · 394 citations

    7

    h-index

  2. Annals of Nuclear Energy

    3 publications · 80 citations

    3

    h-index

  3. Nuclear Engineering and Technology

    1 publications · 18 citations

    1

    h-index

  4. Nuclear Technology

    1 publications · 27 citations

    1

    h-index

  5. 1

    h-index

1–5