Multi-group Cross Section Generation
Multi-Group Cross Section Generation is a computational methodology in nuclear reactor physics that, as a subset of homogenization methods, reduces continuous energy-dependent neutron cross sections into a discrete set of energy-averaged values over predefined energy groups to enable efficient neutronic diffusion and transport calculations.
27
Publications
709
Citations
82
Authors
31
Institutions
Publications per year
2017–2026
17
Parents
27
1–5 of 27
82
4
h-index
3
h-index
2
h-index
2
h-index
2
h-index
1–5 of 82
31

Oak Ridge National Laboratory
Oak Ridge, United States
4 h-index
14 publications
272 citations
University of Michigan
Ann Arbor, United States
3 h-index
4 publications
84 citations
Argonne National Laboratory
Lemont, United States
3 h-index
3 publications
163 citations
Japan Atomic Energy Agency
Tōkai Mura, Japan
2 h-index
5 publications
78 citations
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
Paris, France
2 h-index
5 publications
87 citations

Shanghai Jiao Tong University
Shanghai, China
2 h-index
10 publications
135 citations

Hokkaido University
Sapporo, Japan
2 h-index
2 publications
33 citations
Massachusetts Institute of Technology
Cambridge, United States
2 h-index
6 publications
237 citations
1–8 of 31
6 publications · 117 citations
6
h-index
6 publications · 201 citations
6
h-index
5 publications · 98 citations
5
h-index
JNST · 2 publications · 33 citations
2
h-index
1 publications · 56 citations
1
h-index
1–5