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About the User Support category
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0
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1036
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August 13, 2020
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Criticality Search
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1
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8
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April 26, 2025
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Different distribution of Neutron density in openmc_plasma_source
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7
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183
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April 25, 2025
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Bremsstrahlung Dose Tally with DAGMC Geometry — Extremely High Dose Values
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0
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8
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April 24, 2025
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Determing real simulation time
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6
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68
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April 23, 2025
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Depletion/Burnup not implementing into example problem
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5
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40
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April 23, 2025
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Depletion calculations do not deplete
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11
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800
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April 23, 2025
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Keff remains unchanged in depletion calculation
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9
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370
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April 23, 2025
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Problem with reflective surface
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4
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54
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April 22, 2025
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Reaction frequency using multigroup cross-section and inverse-velocity
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0
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14
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April 19, 2025
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Get_decay_heat(), no depletion chain file?
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2
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20
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April 17, 2025
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Natural abundances of Tantalum
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1
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20
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April 16, 2025
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Is possible to separate tally result according to source distribution values?
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2
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24
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April 15, 2025
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Sharing a fix for Particle X underwent maximum number of events. (and wondering why it worked)
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1
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20
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April 15, 2025
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Question about pathing when using Docker/Jupyter
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1
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14
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April 14, 2025
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Possible depletion and OpenMPI conflict?
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0
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12
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April 12, 2025
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Cannot Merge h5m files with CAd_to_OpenMC
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1
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22
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April 11, 2025
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Depletion analysis on 3D cad geometry
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1
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40
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April 11, 2025
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Code entries to use with h.5m to run the problem
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1
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13
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April 11, 2025
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Source installation fails on Mac M4
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3
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41
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April 11, 2025
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Thermal scattering data c_H_in_H2O in cross_sections issue in pincell.ipynb
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5
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37
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April 10, 2025
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Memory Usage Discrepancy
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1
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13
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April 9, 2025
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Can't plot multigroup cross sections
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0
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10
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April 9, 2025
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Depletion calculation error: "KeyError: 'No material exists with ID=100.'"
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1
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15
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April 8, 2025
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Depletion/decay flux tallies inconsistency
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3
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33
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April 8, 2025
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RuntimeError:No fission sites banked on MPI rank 0
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2
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27
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April 8, 2025
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NJOY2016 steps after compiling
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1
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25
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April 7, 2025
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No scoring of certain events if estimator is 'analog'
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0
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8
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April 7, 2025
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Quick Install Mac instructions
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0
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14
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April 7, 2025
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Trouble fetching pulse-height tally for gamma detector
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2
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108
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April 5, 2025
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