|
About the Validation and Verification category
|
|
0
|
561
|
August 13, 2020
|
|
Trying to model SD-TMSR using OpenMC
|
|
3
|
59
|
December 7, 2024
|
|
ERROR get_atoms from depletion result
|
|
1
|
30
|
December 4, 2024
|
|
Astonishing axial zone divsion effects
|
|
2
|
29
|
December 4, 2024
|
|
Zircaloy-4 activation with JEFF33 depletion chain (Nb97_m1)
|
|
2
|
35
|
November 8, 2024
|
|
Neutron spectrum of MSRE cad design
|
|
0
|
53
|
October 16, 2024
|
|
The difference flux between openMC and MCNP(MCX)
|
|
2
|
61
|
October 11, 2024
|
|
Difference in neutron flux between OPENMC and MCNP6
|
|
1
|
133
|
September 24, 2024
|
|
Transmutation results different from FISPACT-II
|
|
4
|
99
|
August 22, 2024
|
|
Neutron Inelastic Scattering
|
|
2
|
51
|
August 12, 2024
|
|
Error while running a Pincell model
|
|
4
|
53
|
August 7, 2024
|
|
Continuing to investigate convergence
|
|
0
|
28
|
July 31, 2024
|
|
K-inf natural Uranium infinite geometry keff seems too low
|
|
1
|
52
|
July 10, 2024
|
|
Depletion problem with multiplying media in external sources
|
|
5
|
144
|
June 11, 2024
|
|
OpenMC-MCNP heating validation
|
|
0
|
110
|
May 8, 2024
|
|
Keff converges, but the value depends on the initial seed
|
|
1
|
122
|
April 21, 2024
|
|
Keff indiscrepency when modelling TRISO fuel particles
|
|
1
|
177
|
March 1, 2024
|
|
Plotting Geometry Problem
|
|
2
|
264
|
February 28, 2024
|
|
Error in cross-section
|
|
6
|
197
|
February 27, 2024
|
|
Problem with U235 concentration with burnup of the PWR fuel cell
|
|
2
|
257
|
February 27, 2024
|
|
Serpent and OpenMC TRISO Discrepency
|
|
0
|
213
|
February 20, 2024
|
|
Serpent vs Open MC Discrepancy for PinCell (TRISO Fuel)
|
|
0
|
151
|
February 20, 2024
|
|
MCNP5 Error with Thermal Cross Sections
|
|
0
|
115
|
February 15, 2024
|
|
Neutron flux and reaction rates discrepancies with MCNP
|
|
2
|
356
|
January 19, 2024
|
|
Sodium Fast Reactor Benchmarks
|
|
7
|
993
|
December 8, 2023
|
|
OpenMC for modeling and simulating SMRs
|
|
1
|
259
|
October 29, 2023
|
|
Verification of OpenMC TBR evaluation using MCNP as reference
|
|
2
|
378
|
October 20, 2023
|
|
On the Deviation of Results in Using OpenMC to Produce Multi group Cross Sections for Openmoc in the Presence of Vacuum Boundaries
|
|
0
|
253
|
October 10, 2023
|
|
Higher k_eff at 0 depletion step
|
|
0
|
237
|
September 28, 2023
|
|
Question on efficacy of TBR simulations
|
|
2
|
237
|
July 17, 2023
|