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Photon Transport for Radioisotope Source
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1
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31
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March 29, 2025
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Issues with deplete using MPI (it only runs single thread on each process)
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3
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67
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March 29, 2025
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Source Definition
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0
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20
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March 28, 2025
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Setting temperature for a specific nuclide in OpenMC?
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12
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428
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March 28, 2025
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Reflective and periodic boundary conditions with DAGMC geometry
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0
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19
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March 28, 2025
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Issue with Installing on Mac M1 Using Conda
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1
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25
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March 28, 2025
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Building Docker image for use with Singularity
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17
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648
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March 27, 2025
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Sensitivity and Uncertainty Analysis Capability in OpenMC
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11
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1304
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March 27, 2025
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Build burnup matrix from openmc
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2
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51
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March 27, 2025
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Inelastic cross section (n,level)
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6
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164
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March 27, 2025
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How to set lattice so it will compatible with 20000 at least
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4
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19
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March 27, 2025
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Reaction rate tallies failed if `reaction_rate_mode` is flux in the operator kwargs
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0
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11
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March 27, 2025
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Depletion Chains
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1
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33
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March 26, 2025
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Help to create CFER
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2
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47
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March 26, 2025
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Accessing data while looping through multiple runs
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3
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29
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March 26, 2025
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Normalization when power is 0
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3
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36
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March 25, 2025
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Unit for dose calculation
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2
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39
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March 24, 2025
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dose calculation
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20
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3227
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March 24, 2025
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Distinguish depletion materials when using diff_burnable_mats=True
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2
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357
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March 19, 2025
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Compatibility with OpenMC via Docker and Spyder
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0
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15
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March 19, 2025
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Can't install openmc-plotter
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7
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607
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March 18, 2025
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SolidRayTracePlot -> empty plot (aka white square)
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4
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30
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March 18, 2025
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Composite materials - okay to add S(alpha, beta) cross sections?
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1
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39
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March 18, 2025
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Bombard a material with neutrons?
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2
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38
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March 17, 2025
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Kernel Restarting
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0
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17
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March 17, 2025
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Can't seem to merge tallies
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0
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16
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March 16, 2025
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Cell filled with a universe not showing when added to another universe
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2
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41
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March 16, 2025
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Tally Uncertainty; OpenMC vs. MCNP
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14
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1624
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March 14, 2025
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OpenMC Depletion Module "ERROR: Failed to check if object "Fe56" exists"
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1
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23
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March 14, 2025
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More than 95% of external source sites sampled were rejected
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3
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100
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March 14, 2025
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