Hello, I am trying the run the Multigroup Cross Section Generation Part II: Advanced Features example. However, I am not getting the same results as the notebook. Please see my console output below. The message “no result tallied for score total in tally 23” is especially concerning. Note that I am using “jupyter nbconvert” to convert the notebook to a python file (attached mgxs.py
mgxs.py (10.7 KB)
). Thanks for your help!
/home/behnpa/openmc_xs/orig/mgxs.py:23: MatplotlibDeprecationWarning: The seaborn styles shipped by Matplotlib are deprecated since 3.6, as they no longer correspond to the styles shipped by seaborn. However, they will remain available as 'seaborn-v0_8-<style>'. Alternatively, directly use the seaborn API instead.
plt.style.use('seaborn-dark')
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=53.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=21.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=2.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=3.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=4.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=41.
warn(msg, IDWarning)
/home/behnpa/mambaforge3/envs/openmc/lib/python3.10/site-packages/openmc/mixin.py:70: IDWarning: Another Filter instance already exists with id=15.
warn(msg, IDWarning)
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| The OpenMC Monte Carlo Code
Copyright | 2011-2023 MIT, UChicago Argonne LLC, and contributors
License | https://docs.openmc.org/en/latest/license.html
Version | 0.13.3
Git SHA1 | 50e39a4e20dc9e0f3d7ccf07333f6a5e6c797c8c
Date/Time | 2023-08-18 10:50:44
MPI Processes | 1
OpenMP Threads | 96
Reading model XML file './model.xml' ...
Reading cross sections XML file...
Reading U235 from /home/behnpa/openmc/library/endfb-viii.0-hdf5/neutron/U235.h5
Reading U238 from /home/behnpa/openmc/library/endfb-viii.0-hdf5/neutron/U238.h5
Reading O16 from /home/behnpa/openmc/library/endfb-viii.0-hdf5/neutron/O16.h5
Reading H1 from /home/behnpa/openmc/library/endfb-viii.0-hdf5/neutron/H1.h5
Reading Zr90 from /home/behnpa/openmc/library/endfb-viii.0-hdf5/neutron/Zr90.h5
Minimum neutron data temperature: 294 K
Maximum neutron data temperature: 294 K
Preparing distributed cell instances...
Writing summary.h5 file...
Maximum neutron transport energy: 20000000 eV for H1
Initializing source particles...
====================> K EIGENVALUE SIMULATION <====================
Bat./Gen. k Average k
========= ======== ====================
1/1 1.20924
2/1 1.21858
3/1 1.22525
4/1 1.21917
5/1 1.23904
6/1 1.20534
7/1 1.22252
8/1 1.21269
9/1 1.23744
10/1 1.22701
11/1 1.19141
12/1 1.20809 1.19975 +/- 0.00834
13/1 1.24151 1.21367 +/- 0.01473
14/1 1.23687 1.21947 +/- 0.01192
15/1 1.22201 1.21998 +/- 0.00925
16/1 1.20725 1.21786 +/- 0.00784
17/1 1.22312 1.21861 +/- 0.00667
18/1 1.21590 1.21827 +/- 0.00579
19/1 1.21662 1.21809 +/- 0.00511
20/1 1.22605 1.21888 +/- 0.00464
21/1 1.20870 1.21796 +/- 0.00430
22/1 1.23659 1.21951 +/- 0.00422
23/1 1.24622 1.22156 +/- 0.00439
24/1 1.24911 1.22353 +/- 0.00452
25/1 1.21189 1.22276 +/- 0.00427
26/1 1.21209 1.22209 +/- 0.00405
27/1 1.21627 1.22175 +/- 0.00382
28/1 1.23507 1.22249 +/- 0.00368
29/1 1.20381 1.22150 +/- 0.00362
30/1 1.21213 1.22104 +/- 0.00346
31/1 1.22748 1.22134 +/- 0.00331
32/1 1.24403 1.22237 +/- 0.00332
33/1 1.21590 1.22209 +/- 0.00318
34/1 1.21556 1.22182 +/- 0.00306
35/1 1.24717 1.22283 +/- 0.00311
36/1 1.23462 1.22329 +/- 0.00302
37/1 1.24068 1.22393 +/- 0.00297
38/1 1.22589 1.22400 +/- 0.00287
39/1 1.24626 1.22477 +/- 0.00287
40/1 1.22186 1.22467 +/- 0.00278
41/1 1.22113 1.22456 +/- 0.00269
42/1 1.22610 1.22461 +/- 0.00260
43/1 1.21418 1.22429 +/- 0.00254
44/1 1.22749 1.22438 +/- 0.00247
45/1 1.22168 1.22431 +/- 0.00240
46/1 1.22690 1.22438 +/- 0.00233
47/1 1.22576 1.22442 +/- 0.00227
48/1 1.22801 1.22451 +/- 0.00221
49/1 1.19028 1.22363 +/- 0.00232
50/1 1.21369 1.22338 +/- 0.00228
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
Creating state point statepoint.050.h5...
51/1 1.21903 1.22328 +/- 0.00222
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
.
.
.
197/1 1.21360 1.22380 +/- 0.00106
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
198/1 1.23323 1.22385 +/- 0.00106
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
199/1 1.20715 1.22376 +/- 0.00105
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
200/1 1.21964 1.22374 +/- 0.00105
Triggers unsatisfied, no result tallied for score total in tally 23
The estimated number of batches is -2147483637
Creating state point statepoint.200.h5...
=======================> TIMING STATISTICS <=======================
Total time for initialization = 5.6012e+00 seconds
Reading cross sections = 4.7870e+00 seconds
Total time in simulation = 5.4200e+01 seconds
Time in transport only = 1.9771e+01 seconds
Time in inactive batches = 6.4711e-01 seconds
Time in active batches = 5.3553e+01 seconds
Time synchronizing fission bank = 2.1249e-01 seconds
Sampling source sites = 1.7590e-01 seconds
SEND/RECV source sites = 3.4187e-02 seconds
Time accumulating tallies = 3.3927e+01 seconds
Time writing statepoints = 9.5759e-02 seconds
Total time for finalization = 7.5615e-03 seconds
Total time elapsed = 5.9833e+01 seconds
Calculation Rate (inactive) = 154534 particles/second
Calculation Rate (active) = 35478.7 particles/second
============================> RESULTS <============================
k-effective (Collision) = 1.22341 +/- 0.00090
k-effective (Track-length) = 1.22374 +/- 0.00105
k-effective (Absorption) = 1.22316 +/- 0.00075
Combined k-effective = 1.22329 +/- 0.00064
Leakage Fraction = 0.00000 +/- 0.00000
Multi-Group XS
Reaction Type = nu-fission
Domain Type = cell
Domain ID = 1
Nuclide = U235
Cross Sections [barns]:
Group 1 [821000.0 - 20000000.0eV]: 3.30e+00 +/- 1.20e-01%
Group 2 [5530.0 - 821000.0 eV]: 3.98e+00 +/- 8.43e-02%
Group 3 [4.0 - 5530.0 eV]: 5.55e+01 +/- 1.23e-01%
Group 4 [0.625 - 4.0 eV]: 8.84e+01 +/- 1.82e-01%
Group 5 [0.28 - 0.625 eV]: 2.91e+02 +/- 2.40e-01%
Group 6 [0.14 - 0.28 eV]: 4.66e+02 +/- 2.47e-01%
Group 7 [0.058 - 0.14 eV]: 7.02e+02 +/- 1.75e-01%
Group 8 [0.0 - 0.058 eV]: 1.44e+03 +/- 1.62e-01%
Nuclide = U238
Cross Sections [barns]:
Group 1 [821000.0 - 20000000.0eV]: 1.06e+00 +/- 1.42e-01%
Group 2 [5530.0 - 821000.0 eV]: 1.30e-03 +/- 1.44e-01%
Group 3 [4.0 - 5530.0 eV]: 4.65e-04 +/- 1.98e+00%
Group 4 [0.625 - 4.0 eV]: 6.98e-06 +/- 1.64e-01%
Group 5 [0.28 - 0.625 eV]: 1.16e-05 +/- 2.33e-01%
Group 6 [0.14 - 0.28 eV]: 1.68e-05 +/- 2.48e-01%
Group 7 [0.058 - 0.14 eV]: 2.49e-05 +/- 1.75e-01%
Group 8 [0.0 - 0.058 eV]: 4.59e-05 +/- 1.62e-01%
Multi-Group XS
Reaction Type = nu-fission
Domain Type = cell
Domain ID = 1
Cross Sections [cm^-1]:
Group 1 [821000.0 - 20000000.0eV]: 2.52e-02 +/- 1.35e-01%
Group 2 [5530.0 - 821000.0 eV]: 1.52e-03 +/- 8.27e-02%
Group 3 [4.0 - 5530.0 eV]: 2.08e-02 +/- 1.23e-01%
Group 4 [0.625 - 4.0 eV]: 3.31e-02 +/- 1.82e-01%
Group 5 [0.28 - 0.625 eV]: 1.09e-01 +/- 2.40e-01%
Group 6 [0.14 - 0.28 eV]: 1.75e-01 +/- 2.47e-01%
Group 7 [0.058 - 0.14 eV]: 2.63e-01 +/- 1.75e-01%
Group 8 [0.0 - 0.058 eV]: 5.40e-01 +/- 1.62e-01%
Multi-Group XS
Reaction Type = transport
Domain Type = cell
Domain ID = 1
Nuclide = U235
Cross Sections [cm^-1]:
Group 1 [0.625 - 20000000.0eV]: 7.85e-03 +/- 1.21e-01%
Group 2 [0.0 - 0.625 eV]: 1.84e-01 +/- 1.11e-01%
Nuclide = U238
Cross Sections [cm^-1]:
Group 1 [0.625 - 20000000.0eV]: 2.17e-01 +/- 6.92e-02%
Group 2 [0.0 - 0.625 eV]: 2.52e-01 +/- 1.12e-01%
Nuclide = O16
Cross Sections [cm^-1]:
Group 1 [0.625 - 20000000.0eV]: 1.44e-01 +/- 6.87e-02%
Group 2 [0.0 - 0.625 eV]: 1.72e-01 +/- 1.22e-01%