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About the Validation and Verification category
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0
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678
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August 13, 2020
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Cross-section prepration
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0
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23
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June 12, 2026
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Pulse Height Tally in mixed neutron-gamma fields
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2
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157
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May 19, 2026
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K-eff problem with two different geometry
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26
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360
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April 19, 2026
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Difference between number of fission by kappa-fission and by heating-local
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0
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30
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April 17, 2026
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DEPLETION: Starting transport-coupled and transport-independent depletion
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2
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92
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March 25, 2026
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HTR-PM flux problem
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0
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64
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March 9, 2026
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Any fission in a pebble fuel
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7
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133
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March 5, 2026
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Reaction Rate Discrepancy with Serpent
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0
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33
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February 17, 2026
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HTR-10 neutron flux
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3
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177
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January 6, 2026
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Inverse velocity equal to zero in the highest energy group
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0
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46
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December 16, 2025
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Unstructured Mesh Tallies Benchmark
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2
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129
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November 17, 2025
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Differences between proposed and calculated Am/Be point source spectrum
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0
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52
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October 27, 2025
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OpenMC-MCNP heating validation
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1
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249
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September 25, 2025
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Benchmark against MCNP and Tripoli4 unsatisfactory
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10
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884
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September 25, 2025
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Photon heating discrepancies with MCNP and open mc
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0
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128
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July 22, 2025
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Volume Calculation and Keff discrepancies SERPENT /OPENMC
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0
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118
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June 15, 2025
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Pulse-height tally detector NaI(Tl)
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0
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61
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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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25
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May 21, 2025
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Difference in multiplication factor
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1
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298
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May 9, 2025
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Geometry of fuel log TMSR-500 ThorCon International design
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0
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72
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May 2, 2025
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Converting OpenMC Flux Unit to Match MCNP
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3
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201
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March 16, 2025
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Multiple transfer rate
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0
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56
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March 3, 2025
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Trying to model SD-TMSR using OpenMC
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3
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150
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December 7, 2024
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ERROR get_atoms from depletion result
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1
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88
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December 4, 2024
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Astonishing axial zone divsion effects
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2
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94
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December 4, 2024
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Zircaloy-4 activation with JEFF33 depletion chain (Nb97_m1)
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2
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115
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November 8, 2024
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Neutron spectrum of MSRE cad design
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0
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81
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October 16, 2024
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The difference flux between openMC and MCNP(MCX)
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2
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162
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October 11, 2024
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Difference in neutron flux between OPENMC and MCNP6
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1
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317
|
September 24, 2024
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