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About the New Ideas category
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0
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386
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August 13, 2020
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X- ray Exposure room simulation
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1
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16
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April 23, 2025
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Albedo value depending of neutron energy
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2
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89
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April 15, 2025
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Adjustable Orientation for Right Circular Cylinder
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1
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36
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March 27, 2025
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Differentiate_depletable_mats to universe
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5
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53
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March 27, 2025
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Method for monte carlo depletion uncertainty propagation
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0
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64
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March 21, 2025
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Cell search via a tree
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0
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25
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January 18, 2025
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Improving Transport Speed On Unstructured Meshes
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7
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226
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January 9, 2025
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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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27
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December 9, 2024
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Transformations on meshes
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0
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30
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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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97
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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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73
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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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61
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September 6, 2024
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Continuous Material Properties
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0
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58
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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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180
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July 9, 2024
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Hexagonal fuel assembly
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1
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135
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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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472
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May 29, 2024
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Add Support for cylindrical shell in openmc.model.pack_spheres
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1
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118
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May 4, 2024
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McDeLicious integration to OpenMC
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2
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219
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March 11, 2024
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Actinium225 depletion
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0
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80
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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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91
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February 2, 2024
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Persistent Materials object
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3
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145
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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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427
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January 19, 2024
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Convergence criterion for keff
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0
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152
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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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209
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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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298
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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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163
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September 18, 2023
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Interaction-specific collision filters
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0
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135
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September 13, 2023
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Neutron tracking
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5
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283
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September 13, 2023
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Backward detector respond
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2
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241
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July 31, 2023
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