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About the New Ideas category
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0
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407
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August 13, 2020
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Use openmc.lib in depletion calculation
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4
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38
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January 24, 2026
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Cell search via a tree
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3
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95
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January 11, 2026
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Using uv for management of Python workspace
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0
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18
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January 10, 2026
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Photoneutron reactions
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7
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460
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December 2, 2025
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Final Year Project Help: Troubleshooting a TMSR500 Fuel Log Geometry in OpenMC
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1
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58
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October 24, 2025
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Mixing thermal scattering librarries
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0
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33
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October 17, 2025
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Question about “percent_type” argument of the new method “add_elements_from_formula()” introduced in version 0.12
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5
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759
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September 11, 2025
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Functional Expansion Tallies for 3D
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0
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69
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August 12, 2025
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Variance for Photon Shielding Problem
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1
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119
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July 20, 2025
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Get Local Decay Heat
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0
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46
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June 27, 2025
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Problems encountered in converting ACE files to HDF5
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0
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27
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June 16, 2025
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Involute shape implementation
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1
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41
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June 15, 2025
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Modeling Xenon Transport in MSR
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0
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67
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May 21, 2025
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X- ray Exposure room simulation
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1
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48
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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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121
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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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79
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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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107
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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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110
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March 21, 2025
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Improving Transport Speed On Unstructured Meshes
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7
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308
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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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37
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December 9, 2024
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Transformations on meshes
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0
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39
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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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167
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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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105
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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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78
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September 6, 2024
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Continuous Material Properties
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0
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74
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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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247
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July 9, 2024
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Hexagonal fuel assembly
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1
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206
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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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522
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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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170
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May 4, 2024
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