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Abnormal Behavior in K vs. Time Graph in Depletion Run
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0
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49
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April 25, 2024
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Question on OpenMC modeling
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1
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66
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April 25, 2024
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DPA calculation
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11
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198
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April 24, 2024
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CMake error when installing software on Linux
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2
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50
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April 22, 2024
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OpenMC quits using universe.plot
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4
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163
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April 22, 2024
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Thermohydraulics Weirdness
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5
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81
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April 22, 2024
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Math domain error in openmc_plot
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6
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58
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April 22, 2024
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Keff converges, but the value depends on the initial seed
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1
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59
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April 21, 2024
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Irresponsive cell in a geometry and generating voxel hdf5
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1
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66
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April 21, 2024
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To calculate the total atomic density (TOT_ADENS) in complex reactor geometries using OpenMC
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3
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75
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April 21, 2024
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Absorption reaction rate information
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0
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47
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April 19, 2024
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Geometry xml file fail
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1
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52
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April 19, 2024
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Adding cells volume information
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2
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61
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April 17, 2024
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Can variance reduction techniques be used in eigenvalue problems?
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1
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76
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April 17, 2024
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Why is my statepoint.50.h5 file shown to be empty?
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0
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51
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April 17, 2024
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How to stop the calculation when Keff<1?
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0
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54
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April 16, 2024
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Depletion energy
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0
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73
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April 15, 2024
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Setting Cell Regions
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1
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43
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April 15, 2024
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Different distribution of Neutron density in openmc_plasma_source
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4
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87
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April 15, 2024
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How to get local burnup in a 17×17 assembly
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5
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129
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April 12, 2024
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Backscattered neutrons tallied at a detector
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0
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95
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April 10, 2024
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Curious behaviour when transferring elements towards reservoirs in series
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0
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59
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April 9, 2024
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Question on the energy of xs in hdf5 file
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4
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115
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April 9, 2024
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Restart criticality run for variance reduction
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0
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61
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April 9, 2024
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A neutron source with a fixed pulse frequency, fixed pulse duration, and fixed pulse period
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0
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65
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April 9, 2024
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Computing the fission matrix
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10
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509
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April 8, 2024
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How to get tally results frin statepoint file
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4
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113
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April 7, 2024
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Student Project: First time contributors
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3
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170
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April 5, 2024
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Particle Leaking Warning
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1
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76
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April 5, 2024
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OpenMC installation on Windows
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3
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114
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April 4, 2024
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