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About the User Support category
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829
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August 13, 2020
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How to calculate the depth distribution of fuel consumption？
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1
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15
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April 26, 2024
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How to calculate power peaking factor?
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0
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12
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April 26, 2024
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How to use OpenMC to determine the gamma ray radiation spectrum of Co60？
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0
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15
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April 26, 2024
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Install on macOS from CONDA
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0
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9
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April 25, 2024
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Abnormal Behavior in K vs. Time Graph in Depletion Run
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0
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24
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April 25, 2024
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Question on OpenMC modeling
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1
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29
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April 25, 2024
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Particles lost in defined geometry
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0
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24
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April 24, 2024
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Openmc-plotter aborts on launch, AttributeError: 'MainWindow' object has no attribute 'shortcutOverlay'
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5
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44
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April 23, 2024
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Sensitivity and Uncertainty Analysis Capability in OpenMC
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9
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887
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April 23, 2024
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Energy component ratio
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2
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31
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April 22, 2024
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CMake error when installing software on Linux
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2
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28
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April 22, 2024
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OpenMC quits using universe.plot
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4
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153
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April 22, 2024
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Thermohydraulics Weirdness
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5
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55
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April 22, 2024
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Math domain error in openmc_plot
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6
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36
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April 22, 2024
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Irresponsive cell in a geometry and generating voxel hdf5
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1
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55
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April 21, 2024
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To calculate the total atomic density (TOT_ADENS) in complex reactor geometries using OpenMC
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3
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58
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April 21, 2024
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Absorption reaction rate information
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0
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22
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April 19, 2024
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Geometry xml file fail
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1
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35
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April 19, 2024
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Adding cells volume information
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2
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40
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April 17, 2024
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Can variance reduction techniques be used in eigenvalue problems?
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1
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54
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April 17, 2024
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Why is my statepoint.50.h5 file shown to be empty?
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0
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31
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April 17, 2024
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How to stop the calculation when Keff<1?
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0
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35
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April 16, 2024
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Depletion energy
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0
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42
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April 15, 2024
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Setting Cell Regions
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1
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28
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April 15, 2024
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Different distribution of Neutron density in openmc_plasma_source
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4
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59
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April 15, 2024
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How to get local burnup in a 17×17 assembly
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5
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86
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April 12, 2024
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Keff remains unchanged in depletion calculation
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4
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64
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April 12, 2024
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Backscattered neutrons tallied at a detector
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0
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51
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April 10, 2024
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Curious behaviour when transferring elements towards reservoirs in series
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0
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35
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April 9, 2024
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