Published August 18, 2022
| Version v1
Dataset
Open
Multigroup Neutron Transport using a Collision-Based Hybrid Method Dataset
Authors/Creators
- 1. University of Notre Dame
- 2. Oak Ridge National Laboratory
Description
G = 361 Energy Group dataset for the "Multigroup Neutron Transport using a Collision-Based Hybrid Method" paper (under review) by Whewell et al.
Included is the total, scattering, and fission cross section matrices for the G = 361 uranium oxide problem and the energy group bounds for G = 361, 300, 240, 180, 150, 120, 90, 60, and 30.
Files
energy_bounds_030_groups.csv
Files
(6.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:53ec2dc04539d7a83efa5bca623f878b
|
775 Bytes | Preview Download |
|
md5:89c344b014e14bf8b9ca5eec5dfd3a59
|
1.5 kB | Preview Download |
|
md5:71862abdc27f2fe0326bd7b4a592ede2
|
2.3 kB | Preview Download |
|
md5:f7e61b76890e49ef0134574ee9c07917
|
3.0 kB | Preview Download |
|
md5:520cf757ea1b48e3545df35922d3eb16
|
3.8 kB | Preview Download |
|
md5:36c5797dcffc1657c2f331dae124a1bb
|
4.5 kB | Preview Download |
|
md5:756dec7b3647107cdfd87f50519442f6
|
6.0 kB | Preview Download |
|
md5:b28883d2ddee124e1bf7c52ffe273abe
|
7.5 kB | Preview Download |
|
md5:d3e1570c19d317de892ee3c79b84ef6c
|
9.1 kB | Preview Download |
|
md5:c959daf1249c2cc28f2919cdbab28ab0
|
3.3 MB | Preview Download |
|
md5:27fb7fcf6459964e6e83fc619a2cae89
|
3.3 MB | Preview Download |
|
md5:655e87cc88def7e8c5f25510c2487c7f
|
9.0 kB | Preview Download |