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About the New Ideas category
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0
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375
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August 13, 2020
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Albedo value depending of neutron energy
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1
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60
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December 17, 2024
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How to make a cylindrical neutron source with a spallation neutron spectrum?
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0
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10
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December 9, 2024
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Transformations on meshes
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0
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23
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October 17, 2024
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The point detector in OpenMC
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0
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63
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October 11, 2024
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New Composite Surface: Truncated Right Angle Cone
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1
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55
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September 28, 2024
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Split Phase-Space Files (per node)
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1
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55
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September 6, 2024
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Continuous Material Properties
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0
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48
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August 30, 2024
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New function: Plot 3D Cut View
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3
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153
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July 9, 2024
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Hexagonal fuel assembly
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1
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102
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July 8, 2024
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Track-length Photon Heating Estimator
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4
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452
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May 29, 2024
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Improving Transport Speed On Unstructured Meshes
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5
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128
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May 6, 2024
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Add Support for cylindrical shell in openmc.model.pack_spheres
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1
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94
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May 4, 2024
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McDeLicious integration to OpenMC
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2
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202
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March 11, 2024
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Actinium225 depletion
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0
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75
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March 10, 2024
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Is it possible to read PHSP file on openmc?
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0
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89
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February 2, 2024
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Persistent Materials object
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3
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140
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January 25, 2024
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Dedicated Parametric Simulation Module Development
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9
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392
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January 19, 2024
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Convergence criterion for keff
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0
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145
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November 16, 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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197
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October 22, 2023
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Intermediate and Advanced OpenMC Workshops
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1
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281
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September 25, 2023
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Neutron transport in a moving medium
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0
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160
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September 18, 2023
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Interaction-specific collision filters
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0
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134
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September 13, 2023
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Neutron tracking
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5
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251
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September 13, 2023
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Backward detector respond
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2
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234
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July 31, 2023
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Transfer rates with multiple destinations
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1
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212
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July 14, 2023
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Electron beam hitting the Tungsten target creates XRay photons. How do I define the resulting photons source since openMC cant simulate electrons
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3
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586
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July 5, 2023
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Photoneutron reactions
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1
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207
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June 11, 2023
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Getting standard deviation on atoms in depletion simulation
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3
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428
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May 17, 2023
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Delta tracking in OpenMc
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3
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626
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March 20, 2023
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