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
7
1–5 of 7
31
1
h-index
1
h-index
1
h-index
United States Nuclear Regulatory Commission, United States
1 publications · 55 citations
1
h-index
1
h-index
1–5 of 31
14

Xi'an Jiaotong University
Xi'an, China
2 h-index
6 publications
78 citations
University of Portsmouth
Portsmouth, United Kingdom
1 h-index
3 publications
75 citations

Pennsylvania State University
State College, United States
1 h-index
1 publications
55 citations

Chinese Academy of Sciences
Beijing, China
1 h-index
4 publications
84 citations
Westinghouse Electric (United States)
Cranberry Township, United States
1 h-index
3 publications
165 citations
Bhabha Atomic Research Center Hospital
Mumbai, India
1 h-index
5 publications
140 citations
University of Science and Technology of China
Hefei, China
1 h-index
1 publications
21 citations

Bhabha Atomic Research Centre
Mumbai, India
1 h-index
2 publications
50 citations
1–8 of 14
3 publications · 58 citations
3
h-index
2 publications · 42 citations
2
h-index
JNST · 1 publications · 12 citations
1
h-index
1 publications · 55 citations
1
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1–4