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About the User Support category
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0
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205
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August 13, 2020
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HDF5 error when reading cross sections
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2
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22
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January 21, 2022
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Modeling TRISO compacts with unique fuel materials
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0
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27
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January 20, 2022
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Depletion: No energy reported from OpenMC tallies
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2
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29
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January 13, 2022
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Openmc.data.dose_coefficients
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2
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32
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January 13, 2022
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Depletion calculation no xsection xml error
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7
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61
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January 12, 2022
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Openmc-plotter Qt dylib error
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9
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179
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January 11, 2022
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Customized source with energy list
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2
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24
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January 3, 2022
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OpenMC on Android
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2
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111
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January 11, 2022
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Issue with restarting burnup
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5
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93
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January 9, 2022
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Computing (effective) delayed neutron fraction
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1
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63
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January 9, 2022
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Unable to Create Statepoint File
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5
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37
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January 9, 2022
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Capabilities of OpenMC
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8
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223
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January 9, 2022
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Source custom file
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1
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24
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January 9, 2022
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Spacer grid function
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2
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25
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January 9, 2022
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Fixed source tally normalisation
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7
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222
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January 7, 2022
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How to run with CMFD in python scripts
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1
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24
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January 6, 2022
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Custom S Alpha Beta Libraries
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3
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36
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January 5, 2022
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Generate tracks' error for OpenMOC
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2
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28
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January 5, 2022
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Problem at producing ENDF/B-VII.1 at 0 K
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1
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27
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January 4, 2022
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Multigroup Multiplicity Matrix Message
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2
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31
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December 30, 2021
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Finding the inpu tand output file directory
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1
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21
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December 28, 2021
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Is particle lifetime tracked?
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10
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136
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December 23, 2021
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Problem with Plotting
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6
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98
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December 18, 2021
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Warning about capitalized argument
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3
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28
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December 17, 2021
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Waste Packaging Dose/Decay Models
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3
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50
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December 17, 2021
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Could not find thermal scattering data c_H_in_H2O in cross_sections.xml file
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6
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92
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December 15, 2021
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Error with HDF5 when installing into Anaconda environment from source
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9
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136
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December 14, 2021
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Missing nuclide when running pin cell depletion example
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4
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64
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December 13, 2021
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Crash while running depletion with cluster geometry
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3
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53
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December 13, 2021
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