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About the Validation and Verification category
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0
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649
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August 13, 2020
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Any fission in a pebble fuel
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3
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34
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February 15, 2026
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HTR-10 neutron flux
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3
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72
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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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32
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December 16, 2025
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Unstructured Mesh Tallies Benchmark
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2
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88
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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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34
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October 27, 2025
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OpenMC-MCNP heating validation
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1
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205
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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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767
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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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101
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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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92
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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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49
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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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22
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May 21, 2025
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Difference in multiplication factor
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1
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278
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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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59
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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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169
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March 16, 2025
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Multiple transfer rate
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0
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42
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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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122
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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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68
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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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72
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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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95
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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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75
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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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123
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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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285
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September 24, 2024
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Transmutation results different from FISPACT-II
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4
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193
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August 22, 2024
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Neutron Inelastic Scattering
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2
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113
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August 12, 2024
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Error while running a Pincell model
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4
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92
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August 7, 2024
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Continuing to investigate convergence
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0
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73
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July 31, 2024
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K-inf natural Uranium infinite geometry keff seems too low
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1
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127
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July 10, 2024
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Depletion problem with multiplying media in external sources
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5
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259
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June 11, 2024
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Keff converges, but the value depends on the initial seed
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1
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185
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April 21, 2024
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