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About the User Support category
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0
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695
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August 13, 2020
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Reaction rates for all nuclides using Tally
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1
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11
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November 28, 2023
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Flux tally in the region between a hexagonal lattice and a cylinder
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0
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4
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November 28, 2023
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How to calculate the neutron flux of each lattiece universe (corresponding cell)
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4
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28
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November 28, 2023
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Inquiring about the tool to modify HDF5 file
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2
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19
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November 28, 2023
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Full Core Geometry broken
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1
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29
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November 27, 2023
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Setting temperature for a specific nuclide in OpenMC?
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2
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47
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November 27, 2023
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No such file or directory: 'openmc'
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5
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254
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November 27, 2023
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Install openmc on windows10
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6
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473
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November 27, 2023
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Differences in CSG/DAGMC results
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6
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91
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November 24, 2023
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Locality rotation and translation
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0
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19
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November 24, 2023
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Segmentation fault on simple model after many particles
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8
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193
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November 23, 2023
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KRUSTY neutronics
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1
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59
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November 23, 2023
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Photon Spectrum Analysis
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1
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51
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November 23, 2023
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BEGINNER - creating mesh and mesh filter
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0
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20
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November 22, 2023
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HexagonalPrism (new_version)
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0
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25
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November 22, 2023
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Am i correct in thinking the flux i get, is in order of groups 1_i value then group 2_i value then group 1_i+1 value and then group 2_i+1 value?
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0
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11
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November 21, 2023
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Problem with reading current tallies
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5
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316
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November 21, 2023
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Problem in flux calculation for unstructured mesh
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11
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132
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November 20, 2023
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Histogram scatter format in multigroup
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0
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38
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November 20, 2023
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Unable to understand 2 group flux
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0
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15
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November 20, 2023
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Can pulse-height tally be used to measure photons produced via decay?
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0
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19
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November 19, 2023
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Specifying domain gives error of ' Unable to set "domain" to "OrderedDict([(2, Material )])" since each item must be of type "Material"
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2
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17
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November 18, 2023
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Openmc installation using mamba
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5
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133
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November 16, 2023
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How to create unstructured meshes for tallying
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14
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839
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November 16, 2023
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MPI Installation
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0
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20
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November 15, 2023
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" ERROR: More than 95% of sampled external source sites were rejected. Please check your external source spatial definitions. " when designing a pebble-bed
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1
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30
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November 15, 2023
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Summary.h5 /geometry/cells/cell <uid>/ has dataset named fill, but it's not mentioned in documentation
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3
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49
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November 14, 2023
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Regression tests failed - OpenMC version 0.14.0
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0
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41
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November 14, 2023
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Using IRDFF-II Cross Section Data in OpenMC
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3
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258
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November 14, 2023
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