About the User Support category
|
|
0
|
83
|
August 13, 2020
|
WARNING: Particle had a negative distance to a lattice boundary after 0.12.1 update
|
|
0
|
6
|
April 10, 2021
|
ENDF nuclear data for Carbon
|
|
1
|
12
|
April 9, 2021
|
Why is there such a dip in my u235 and pu239
|
|
4
|
33
|
April 8, 2021
|
What does the warming: maximum neutron energy is below 20 Mev. this may bias the results mean
|
|
0
|
12
|
April 8, 2021
|
If i have a full reactor operating at 3600MW thermal, what power should i use just for a pincell?
|
|
4
|
24
|
April 7, 2021
|
Create a depletion chain .xml file.
|
|
12
|
47
|
April 7, 2021
|
Difference between sum and atom/b-cm when setting density
|
|
4
|
25
|
April 6, 2021
|
Minimal wmp simulation with minimal cross_section.xml
|
|
8
|
30
|
April 6, 2021
|
Numerical accuracy of the output result
|
|
1
|
15
|
April 6, 2021
|
1-group xs library
|
|
1
|
13
|
April 6, 2021
|
Source file don't exist in setting.xml
|
|
3
|
79
|
April 6, 2021
|
Flux from each incedent photon energy (energy Filter)
|
|
1
|
16
|
April 6, 2021
|
Did not sample any nuclide during collision
|
|
1
|
19
|
April 6, 2021
|
Could openmc not generate multi-group cross sections in fixed source mode?
|
|
1
|
29
|
April 6, 2021
|
How to define a spherical source
|
|
1
|
28
|
April 6, 2021
|
Neutron shielding simulation stops to work when I include photons
|
|
6
|
31
|
April 6, 2021
|
OpenMC installation inside Singularity Container on HPC - No such file or directory: 'openmc'
|
|
5
|
47
|
April 6, 2021
|
Decay Chains simulation and dose calculations
|
|
5
|
36
|
April 6, 2021
|
How to use new features "filed base source" on OpenMC 0.12.1
|
|
5
|
42
|
April 5, 2021
|
Small Modular Reactor Core
|
|
6
|
60
|
April 2, 2021
|
Modeling Fuel pin cell error: CalledProcessError: Command 'openmc' died with <Signals.SIGSEGV: 11>
|
|
2
|
15
|
April 1, 2021
|
Pause and Change material density between each time step
|
|
4
|
66
|
March 31, 2021
|
How would i go about making a hexagonal unit cell?
|
|
6
|
27
|
March 31, 2021
|
Generating h5 files from ENDF-B-viii.0
|
|
2
|
28
|
March 31, 2021
|
Restart of Depletion calculation
|
|
7
|
95
|
March 29, 2021
|
Error Import Openmoc
|
|
2
|
17
|
March 25, 2021
|
Coupled neutron-photon simulations and WMP libraries
|
|
2
|
18
|
March 25, 2021
|
Lattice Cell as Tally CellFilter
|
|
4
|
27
|
March 24, 2021
|
How to distinguish neutron and photon contribution for a tally
|
|
2
|
18
|
March 23, 2021
|