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How to use Weight Windows
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2
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259
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March 8, 2024
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How to run openMC in Jupyter notebook in WSL
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5
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293
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August 11, 2023
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Weight windows to improve the accuracy of the flux spectrum at low energies
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0
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133
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November 7, 2023
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Depletion results reading problem
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1
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99
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December 23, 2023
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DAGMC boundary condition
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5
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347
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November 30, 2023
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Openmc installation using mamba
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5
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335
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November 16, 2023
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Polyethylene (HDPE) cross section for neutron moderation
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8
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242
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May 25, 2023
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Xe135 production problem
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6
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145
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January 3, 2024
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Getting standard deviation on atoms in depletion simulation
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3
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351
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May 17, 2023
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Transfer rates warning for destination material
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2
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117
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June 2, 2023
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Output folder path for integrator.integrate()
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5
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144
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June 16, 2023
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Problem with photon-neutron transport
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8
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235
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May 16, 2023
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Question for mesh tallys and cells, very different values
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4
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317
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August 2, 2023
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Candu depletion compare problem
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6
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238
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December 18, 2023
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Depletion power distribution
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4
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302
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January 25, 2024
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Depletion into MGXS Generation for Full Reactor Sim
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3
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188
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September 8, 2023
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Issues with GVR
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7
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228
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July 13, 2023
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Asymmetrical profile for symmetrical PWR core
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6
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223
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September 13, 2023
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Particle lost without warning/error or being killed, stalling the run
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2
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198
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June 22, 2023
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Determine TRISO Locations
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5
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256
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June 5, 2023
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OpenMC quits using universe.plot
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4
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159
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April 22, 2024
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Variance Reduction Method to Weight Cells (IMP Keyword for openMC?)
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6
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256
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March 24, 2024
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Micro gravity simulation
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1
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109
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August 12, 2023
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Installation trouble
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6
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196
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September 13, 2023
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Pulse height tally
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6
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213
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October 3, 2023
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Python API issues
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3
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268
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May 19, 2023
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IsADirectoryError: [Errno 21] Is a directory: '/opt/endfb-vii.1-hdf5'
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5
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196
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August 12, 2023
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Issues with MeshFilter and Paraview Visualization
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4
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249
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July 17, 2023
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Openmc simulation stucked in k-model
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8
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190
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February 15, 2024
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Negative atoms when using openmc.deplete.IndependentOperator
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4
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247
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June 16, 2023
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Backward detector respond
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2
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194
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July 31, 2023
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Toggle Function IUPAC 2009/2013 data (data.py NATURAL_ABUNDANCE)
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3
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150
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June 29, 2023
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Tally the neutron current on a hemispherical surface
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4
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271
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July 15, 2023
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Multi-node parallel in openmc.run() and integrator.integrate()
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2
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338
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June 6, 2023
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Issues Fetching Nuclide Concentration from Depleted Results
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5
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213
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September 9, 2023
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CAD geometry running problem
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4
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200
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September 25, 2023
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Problem executing OpenMc example
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3
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222
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July 26, 2023
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Request for Guidance on microscopic depletion calculation scheme implemented throught OpenMC and a nodal code
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1
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173
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October 22, 2023
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Differences in CSG/DAGMC results
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6
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176
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November 24, 2023
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What C++ programming paradigm is used in OpenMC
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1
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156
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October 26, 2023
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Getting different results when running example
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4
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183
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August 24, 2023
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The 0 step depletion and transport keff result are different
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3
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214
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June 12, 2023
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Volume of cells from DAGMC file?
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2
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127
|
June 29, 2023
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HexagonalPrism (new_version)
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2
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123
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March 13, 2024
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RuntimeError: Failed to open HDF5 file with mode 'w': summary.h5
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3
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210
|
December 30, 2023
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Depletion energy
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0
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67
|
April 15, 2024
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Do OpenMC need special settings to achieve maximum computing speed when using multi-threaded computing?
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4
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187
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January 12, 2024
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Dose rate calculation
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2
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273
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September 4, 2023
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Verification of OpenMC TBR evaluation using MCNP as reference
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2
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273
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October 20, 2023
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I want to obtain keff after each calculation easily. Does OpenMC have corresponding functions?
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3
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202
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January 22, 2024
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