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About the User Support category
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0
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315
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August 13, 2020
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Reflective boundary could not reflecting particles
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3
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62
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March 4, 2022
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Gamma radiation from fission
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1
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22
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May 13, 2022
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Tallying in Energy Units and Using CollisionFilter
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0
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10
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May 13, 2022
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Heating during depletion
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0
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9
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May 13, 2022
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TypeError: bad operand type for unary -: 'Intersection'
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3
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298
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May 12, 2022
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Options of Visualization
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0
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22
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May 12, 2022
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Problem with modeling detector's shield
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2
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38
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May 11, 2022
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No intersection found with DAGMC cell
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7
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54
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May 11, 2022
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Question about running depletion in parallel
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5
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38
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May 10, 2022
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Did not sample any nuclide during collision
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5
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100
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May 10, 2022
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Computing the fission matrix
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7
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46
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May 10, 2022
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RuntimeError: OpenMC aborted unexpectedly
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6
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69
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May 10, 2022
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About cylindrical mesh using in multi cylindrical-fuel pins
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2
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23
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May 10, 2022
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My leakage fration too high in result
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2
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27
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May 10, 2022
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Multi-pins how to use cylindrical-Mesh
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1
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24
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May 10, 2022
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Error: no tris are adjacent to the node
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2
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18
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May 10, 2022
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Building Docker image for use with Singularity
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8
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37
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May 10, 2022
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Windowed Multipole cross section error - Could not find nuclide Li6 in the nuclear data library
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2
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29
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May 9, 2022
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Deplet without consider fuel
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2
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28
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May 6, 2022
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Problems running a depletion calculation with neutron-photon interaction, for the proper energy deposition calculation and the subsequent proper power normalization
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15
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417
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May 6, 2022
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Flus tally in a point.
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4
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88
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May 5, 2022
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Reflective Boundary Hexagonal Multigroup problem
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8
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75
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May 5, 2022
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Converting ACE photo-atomic data to HDF5
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1
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34
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May 5, 2022
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Problem model.cylinder_from_points
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2
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37
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May 5, 2022
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Questions on OpenMC plotting
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5
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131
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May 5, 2022
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Using IRDFF-II Cross Section Data in OpenMC
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1
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34
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May 5, 2022
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Set reflective boundary condition for pin by pin hexagonal problem
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1
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31
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May 5, 2022
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How to use macroscopic material
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4
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16
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May 5, 2022
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Problem in compilation of latest stable release
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3
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30
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May 5, 2022
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