Graphite Void Coefficient
The Graphite Void Coefficient is a neutronic reactivity coefficient that quantifies the change in reactor reactivity per unit change in void fraction within a graphite-moderated nuclear reactor core, specifically characterizing the inherent feedback response due to coolant density variations in the presence of graphite as the primary moderator.
5
Publications
190
Citations
18
Authors
4
Institutions
Publications per year
2017–2026
3
Parents
5
Nuclear graphite for high temperature gas-cooled reactors
Xiangwen Zhou, Yaping Tang, Zhenming Lu et al. · New Carbon Materials · 2017 · 117 citations
Impurities in and serviceability of reactor graphite
Yu. S. Virgil’ev · Atomic Energy · 1998 · 14 citations
Nuclear graphite for high temperature gas-cooled reactors
Xiangwen Zhou, Ya‐Ping Tang, Zhenming Lü et al. · Carbon · 2017 · 13 citations
1–5 of 5
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State Scientific Center - Research Institute of Atomic Reactors, Russia
1 publications · 14 citations
1
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1
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1–5 of 18
4
Tsinghua University
Beijing, China
3 h-index
13 publications
695 citations
Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
Shanghai, China
3 h-index
13 publications
695 citations

University of Hull
Hull, United Kingdom
1 h-index
1 publications
31 citations

University of Manchester
Manchester, United Kingdom
1 h-index
6 publications
186 citations
1–4 of 4
1 publications · 13 citations
1
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1 publications · 31 citations
1
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1 publications · 117 citations
1
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1 publications · 15 citations
1
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1 publications · 14 citations
1
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