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Welcome to Discourse
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0
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457
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August 5, 2020
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Simulation file orders
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3
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23
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May 29, 2025
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Making reflector region in just one cell
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2
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14
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May 29, 2025
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Sharing a fix for Particle X underwent maximum number of events. (and wondering why it worked)
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4
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36
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May 29, 2025
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Revolve a 2-D profile into a 3-D solid CSG?
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1
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10
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May 29, 2025
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Updating materials using depletion results
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1
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32
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May 28, 2025
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Transient with Control Drums
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2
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61
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May 28, 2025
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OpenMC monthly meeting dates 2024
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35
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1118
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May 27, 2025
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Online OpenMC Online Course June 30-July 3
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0
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60
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May 27, 2025
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How do i Install the latest version of openmc in my apple silicon chip Macbook Air M1
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3
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50
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May 27, 2025
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Invalid Tally Score: "ifp-time-numerator" - Unknown Score
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5
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43
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May 27, 2025
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Neutron flux in CEFR fuel assembly
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1
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36
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May 26, 2025
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Build openmc/openmc:develop for arm64
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0
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17
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May 24, 2025
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Job vacancies looking for OpenMC skills
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47
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3380
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May 23, 2025
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MGXS Fission equal to zero
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1
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27
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May 23, 2025
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Evaluation determination of gamma scanning fuel burn up
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1
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24
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May 22, 2025
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95% of external source sites rejected
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2
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21
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May 22, 2025
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Papers using OpenMC
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193
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8109
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May 22, 2025
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Calculation of "Prompt neutron lifetime" and neutron generation time using Openmc
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1
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43
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May 22, 2025
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Pulse-height tally detector NaI(Tl)
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0
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14
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May 22, 2025
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Fission Locations of an SFR?
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0
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7
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May 21, 2025
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The geometry.xml of OpenMC can be calculated and run normally in the CPU version, but it cannot be run in the GPU version.
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1
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36
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May 21, 2025
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Modeling Xenon Transport in MSR
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0
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14
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May 21, 2025
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Photoneutron reactions
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5
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282
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May 20, 2025
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Material Density Variation
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3
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51
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May 20, 2025
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ERROR: No fission sites banked on MPI rank 0 for SMR PWR
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1
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21
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May 17, 2025
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How do i Replace the Nuclear Data Library in Openmc in Docker?
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3
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37
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May 17, 2025
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Failure in unit test
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11
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1382
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May 15, 2025
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Gamma detector simulation example
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1
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36
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May 14, 2025
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Plotting flux spectrum after depletion in openmc
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5
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190
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May 14, 2025
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