|
Neutron Inelastic Scattering
|
|
2
|
122
|
August 12, 2024
|
|
Error while running a Pincell model
|
|
4
|
99
|
August 7, 2024
|
|
Continuing to investigate convergence
|
|
0
|
79
|
July 31, 2024
|
|
K-inf natural Uranium infinite geometry keff seems too low
|
|
1
|
138
|
July 10, 2024
|
|
Depletion problem with multiplying media in external sources
|
|
5
|
282
|
June 11, 2024
|
|
Keff converges, but the value depends on the initial seed
|
|
1
|
193
|
April 21, 2024
|
|
Keff indiscrepency when modelling TRISO fuel particles
|
|
1
|
248
|
March 1, 2024
|
|
Plotting Geometry Problem
|
|
2
|
374
|
February 28, 2024
|
|
Error in cross-section
|
|
6
|
290
|
February 27, 2024
|
|
Problem with U235 concentration with burnup of the PWR fuel cell
|
|
2
|
314
|
February 27, 2024
|
|
Serpent and OpenMC TRISO Discrepency
|
|
0
|
308
|
February 20, 2024
|
|
Serpent vs Open MC Discrepancy for PinCell (TRISO Fuel)
|
|
0
|
259
|
February 20, 2024
|
|
MCNP5 Error with Thermal Cross Sections
|
|
0
|
137
|
February 15, 2024
|
|
Neutron flux and reaction rates discrepancies with MCNP
|
|
2
|
450
|
January 19, 2024
|
|
Sodium Fast Reactor Benchmarks
|
|
7
|
1168
|
December 8, 2023
|
|
OpenMC for modeling and simulating SMRs
|
|
1
|
391
|
October 29, 2023
|
|
Verification of OpenMC TBR evaluation using MCNP as reference
|
|
2
|
457
|
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
|
306
|
October 10, 2023
|
|
Higher k_eff at 0 depletion step
|
|
0
|
266
|
September 28, 2023
|
|
Question on efficacy of TBR simulations
|
|
2
|
272
|
July 17, 2023
|
|
Am242 in ENDF/B-VIII.0 cross sections distributed with OpenMC
|
|
2
|
251
|
June 20, 2023
|
|
What factors can affect the change in the fast to thermal flux spectrum?
|
|
1
|
246
|
April 7, 2023
|
|
Error after running depletion
|
|
4
|
546
|
March 30, 2023
|
|
Data.njoy.make_ace_thermal problem
|
|
0
|
299
|
February 22, 2023
|
|
Photon flux discrepancies with EGSnrc, MCNP, and Serpent
|
|
10
|
770
|
January 20, 2023
|
|
Depletion Calculation of Nuclide Th233
|
|
6
|
460
|
January 2, 2023
|
|
Decay Rate missed some values in tallies for Decay Rate
|
|
2
|
342
|
December 6, 2022
|
|
K-eff disagreement on thermal scattering
|
|
5
|
520
|
November 23, 2022
|
|
Fission Yield of Pm149 from U235
|
|
3
|
273
|
November 1, 2022
|
|
Validation database for OpenMC
|
|
1
|
696
|
October 5, 2022
|