Containment Safety Analysis
Containment Safety Analysis is a subfield of nuclear safety analysis that systematically evaluates the ability of a reactor containment system to prevent or limit the release of radioactive materials under normal, transient, and accident conditions, using deterministic and/or probabilistic methods to demonstrate compliance with defined safety criteria.
412
Publications
11.9K
Citations
1.4K
Authors
339
Institutions
Publications per year
2017–2026
106
Parents
Children
Containment Accident LoadingContainment Aging DegradationContainment Code VerificationContainment Crack PropagationContainment Depressurization DynamicsContainment Dynamic Load AnalysisContainment Failure ModesContainment Filtered VentingContainment Fracture MechanicsContainment Heat Transfer
412
1–5 of 412
1.4K
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339
Institut de Radioprotection et de Sûreté Nucléaire
Fontenay-aux-Roses, France
16 h-index
57 publications
2.3K citations
Korea Atomic Energy Research Institute
Daejeon, South Korea
14 h-index
47 publications
1.2K citations

Harbin Engineering University
Harbin, China
13 h-index
46 publications
1.2K citations
Tsinghua University
Beijing, China
11 h-index
34 publications
1K citations
Gesellschaft für Anlagen und Reaktorsicherheit
Cologne, Germany
11 h-index
17 publications
1.1K citations
Paul Scherrer Institute
Villigen, Switzerland
11 h-index
37 publications
1.2K citations
Dalian University of Technology
Dalian, China
10 h-index
26 publications
687 citations

VTT Technical Research Centre of Finland
Espoo, Finland
10 h-index
14 publications
410 citations
1–8 of 339
105 publications · 3.4K citations
34
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44 publications · 998 citations
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27 publications · 733 citations
17
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22 publications · 634 citations
17
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25 publications · 905 citations
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