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About the User Support category
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0
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618
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August 13, 2020
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Error meshing CAD geometry
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1
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9
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September 29, 2023
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Depletion module of openmc
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8
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77
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September 29, 2023
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RuntimeError when plotting (in pincell-tutorial's universe.plot() and openmc.plot_geometry())
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6
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385
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September 29, 2023
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Openmc-plotter Qt dylib error
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10
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607
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September 28, 2023
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How to simulate a uniform radiation field where the same surface flux exists
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2
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25
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September 27, 2023
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XY mesh talley data post processing
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8
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77
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September 27, 2023
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Openmc installation using mamba
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4
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68
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September 26, 2023
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Custom Source Issues
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2
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46
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September 26, 2023
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Negative MT=301 Macroscopic cross-sections for Inconel
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3
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30
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September 26, 2023
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Issue with source for fusion problem
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4
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41
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September 25, 2023
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CAD geometry running problem
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4
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33
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September 25, 2023
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Creating a cross_section.xml file
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2
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33
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September 22, 2023
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DAGMC boundary condition
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3
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51
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September 21, 2023
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Spherical Source, no interaction
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4
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45
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September 21, 2023
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How to access the state point document with the data
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2
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26
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September 20, 2023
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Trouble using FENDL 3.2 hdf5 files in photon simulations
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3
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30
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September 19, 2023
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About openmc.deplete.atom_number.set_atom_density()
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1
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13
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September 19, 2023
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Depletion calculation for irregular geometry,get atome number result
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3
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45
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September 18, 2023
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Krusty core design and neutronics
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2
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73
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September 18, 2023
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Pin power distribution interpolation
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2
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41
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September 18, 2023
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Accessing Photo-Nuclear Reaction Data
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1
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42
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September 16, 2023
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OpenMC depletion plotter Y limit
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0
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21
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September 14, 2023
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Nbatches, particles when using surf_source_read
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0
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28
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September 13, 2023
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Asymmetrical profile for symmetrical PWR core
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6
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76
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September 13, 2023
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Installation trouble
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6
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56
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September 13, 2023
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DAGMC material volume calculation runs forever
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0
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22
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September 12, 2023
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Discrepant results using surf_source_write / surf_source_read
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4
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29
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September 12, 2023
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Large runtime with large number of sources
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0
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28
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September 11, 2023
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OpenMC and FISPACT II Interface
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6
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337
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September 11, 2023
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