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ACE files conversion to h5 problems
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0
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47
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November 15, 2024
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About how to use nuclear data library downloaded from the official website
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5
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95
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November 24, 2024
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Get source particle type from statepoint file
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0
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14
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November 23, 2024
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There are several possible reasons why OpenMC may not be running correctly
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1
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32
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November 23, 2024
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Issues with parallel depletion and h5py
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2
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402
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November 22, 2024
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OpenMC plotter runs super slow
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4
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112
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November 22, 2024
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Photon Flux Reading Zero
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1
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32
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November 21, 2024
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Units for transfer rates
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1
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31
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November 21, 2024
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Axial flux plot
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5
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208
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November 20, 2024
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Order of indices in 3D mesh tally
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1
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277
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November 20, 2024
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Continuous energy external source with constant probability for each energy bin
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3
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67
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November 20, 2024
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Maximum number of lost particles has been reached
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0
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26
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November 18, 2024
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Calculating Normalized Surface Current
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0
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45
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November 16, 2024
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Mix_materials and s alpha beta
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4
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374
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November 16, 2024
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Burnup and k-eff
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0
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69
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November 15, 2024
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Modelling Spacer Grids
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2
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48
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November 13, 2024
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Is there any availability shown on how OpenMc discusses/solved the Boltzmann transport equation (mathematically in details) using Monte-carlo approach?
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1
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51
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November 11, 2024
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Assigning an Energy Source to a Complex-Shaped Cell
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0
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68
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November 10, 2024
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How to check for cell overlap?
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4
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113
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November 8, 2024
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Ask for help about using openmc-onix coupling
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0
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22
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November 8, 2024
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Fixed-Source Tally Normailization
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0
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64
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November 7, 2024
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Gradual meshing
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1
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32
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November 6, 2024
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CANDU adjuster rods display
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0
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33
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November 6, 2024
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Problem with the density of the coolant
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2
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49
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November 6, 2024
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Multiple boundary conditions with DAGMC
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1
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37
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November 4, 2024
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How to know the amount of each energy type in heating
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0
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17
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November 3, 2024
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RuntimeError: Object "C12" does not exist in object
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0
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25
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November 3, 2024
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Problems encountered in hexagonal core modeling
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1
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25
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October 31, 2024
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Problem encountered in drawing hexagonal regions: The boundary on the xy plane does not exist
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1
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39
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October 31, 2024
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MG cross section error
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1
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42
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October 30, 2024
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