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About the Validation and Verification category
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0
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664
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August 13, 2020
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K-eff problem with two different geometry
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26
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155
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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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21
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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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64
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March 25, 2026
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Pulse Height Tally in mixed neutron-gamma fields
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1
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99
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March 11, 2026
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HTR-PM flux problem
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0
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39
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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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108
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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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23
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February 17, 2026
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HTR-10 neutron flux
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3
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135
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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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38
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December 16, 2025
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Unstructured Mesh Tallies Benchmark
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2
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120
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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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50
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October 27, 2025
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OpenMC-MCNP heating validation
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1
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224
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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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816
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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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109
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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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103
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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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55
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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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23
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May 21, 2025
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Difference in multiplication factor
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1
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289
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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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65
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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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184
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March 16, 2025
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Multiple transfer rate
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0
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45
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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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136
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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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80
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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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79
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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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103
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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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79
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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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140
|
October 11, 2024
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Difference in neutron flux between OPENMC and MCNP6
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1
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304
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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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214
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August 22, 2024
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