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core.log
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core.log
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_ .-=-. .-=-. .-==-.
{ } __ .' O o '. .' O o '. / -<' )--<
{ } .' O'. / o .-. O \ / o .-. O \ / .---`
{ } / .-. o\ /O / \ o\ /O / \ o\ /O /
\ `-` / \ O`-'o / \ O`-'o / \ O`-`o /
`-.-` '.____.' `._____.' `.____.'
Serpent 2 beta
A Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code
- Version 2.1.17 (February 24, 2014) -- Contact: Jaakko.Leppanen@vtt.fi
- MPI Parallel calculation mode available
- OpenMP Parallel calculation mode available
- Geometry and mesh plotting available
- Default data path not set
Begin calculation on Fri Jun 12 17:46:56 2015
Reading input file "serp_full_core"...
Reading input file "Blanket"...
Reading input file "OR"...
Reading input file "CRCC"...
Reading input file "Fuel"...
Reading input file "CR"...
Reading input file "ORCC"...
Reading input file "coreMaterials"...
Checking duplicate input definitions...
OK.
Reading pebble bed type geometry:
Reading data from file "pb_pos40"...
Reading data from file "pb_pos_40"...
Creating geometry...
OK.
Counting geometry zones...
The geometry consists of 8 levels:
Level 0 size: max 2 zones
Level 1 size: max 32 zones
Level 2 size: max 1 zones
Level 3 size: max 1 zones
Level 4 size: max 15 zones
Level 5 size: max 3 zones
Level 6 size: max 1 zones
Level 7 size: max 6 zones
Processing cells...
OK.
Linking materials to geometry...
OK.
Counting cells...
OK.
Processing data for group constant generation:
- 70 energy groups in micro-group structure
- 2 energy groups in macro-group structure
- B1 fundamental mode calculation is not run
- Group constants generated in 1 universes
- Discontinuity factors are not calculated
- Pin-power distributions are not calculated
- Poison cross sections are not calculated
Plotting geometry:
0% complete
33% complete
67% complete
100% complete
Reading ACE directory files...
OK.
Adding nuclides in material Flibe924...
Nuclide 3006.09c -- lithium 6 at 923K (Li-6)
Nuclide 3007.09c -- lithium 7 at 923K (Li-7)
Nuclide 4009.09c -- beryllium 9 at 923K (Be-9)
Nuclide 9019.09c -- fluorine 19 at 923K (F-19)
Adding nuclides in material Graphite924...
Nuclide 6000.09c -- natural carbon at 923K (C-nat)
Adding nuclides in material GraphiteCoolantMix924...
Adding nuclides in material CentralGraphite...
Nuclide 6000.09c -- natural carbon at 1073K (C-nat)
Adding nuclides in material Shell...
Adding nuclides in material fuel0...
Nuclide 92235.09c -- uranium 235 at 1073K (U-235)
Nuclide 92238.09c -- uranium 238 at 1073K (U-238)
Nuclide 12000.09c -- natural magnesium at 1073K (Mg-nat)
Nuclide 8016.09c -- oxygen 16 at 1073K (O-16)
Adding nuclides in material Buffer...
Adding nuclides in material iPyC...
Adding nuclides in material SiC...
Nuclide 14000.09c -- natural silicon at 1073K (Si-nat)
Adding nuclides in material oPyC...
Adding nuclides in material Matrix...
Nuclide 5010.09c -- boron 10 at 1073K (B-10)
Nuclide 5011.09c -- boron 11 at 1073K (B-11)
Adding nuclides in material fuel1...
Adding nuclides in material fuel2...
Adding nuclides in material fuel3...
Adding nuclides in material fuel4...
Adding nuclides in material fuel5...
Adding nuclides in material fuel6...
Adding nuclides in material fuel7...
Adding nuclides in material fuel8...
Adding nuclides in material fuel9...
Adding nuclides in material fuel10...
Adding nuclides in material fuel11...
Adding nuclides in material fuel12...
Adding nuclides in material fuel13...
Running Doppler-broadening preprocessor:
Adjusting nuclide 3006.09c temperature from 900K to 923K...
Adjusting nuclide 3007.09c temperature from 900K to 923K...
Adjusting nuclide 4009.09c temperature from 900K to 923K...
Adjusting nuclide 9019.09c temperature from 900K to 923K...
Adjusting nuclide 6000.09c temperature from 900K to 923K...
Adjusting nuclide 6000.09c temperature from 900K to 1073K...
Adjusting nuclide 92235.09c temperature from 900K to 1073K...
Adjusting nuclide 92238.09c temperature from 900K to 1073K...
Adjusting nuclide 12000.09c temperature from 900K to 1073K...
Adjusting nuclide 8016.09c temperature from 900K to 1073K...
Adjusting nuclide 14000.09c temperature from 900K to 1073K...
Adjusting nuclide 5010.09c temperature from 900K to 1073K...
Adjusting nuclide 5011.09c temperature from 900K to 1073K...
Adding thermal scattering data...
Nuclide gre7.20t -- natural carbon at 1000K (C-nat)
Nuclide gre7.22t -- natural carbon at 1200K (C-nat)
Checking data and printing output...
OK.
Generating unionize energy grids...
Adding points:
3006.09c -- Points added in neutron grid: 520
3007.09c -- Points added in neutron grid: 86
4009.09c -- Points added in neutron grid: 101
5010.09c -- Points added in neutron grid: 219
5011.09c -- Points added in neutron grid: 2610
6000.09c -- Points added in neutron grid: 582
6000.09c -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 1205
6000.09s -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 2
6000.09s -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 0
6000.09s -- Points added in neutron grid: 0
8016.09c -- Points added in neutron grid: 1526
9019.09c -- Points added in neutron grid: 1049
12000.09c -- Points added in neutron grid: 1816
14000.09c -- Points added in neutron grid: 2589
92235.09c -- Points added in neutron grid: 25161
92238.09c -- Points added in neutron grid: 54189
Generating unionized energy grid:
- Unionization performed without grid thinning
between 1.00E-11 and 20.0 MeV.
- Final neutron grid size: 91467 points.
- 4.68 Mb of memory allocated for grid data
OK.
Processing cross sections and ENDF reaction laws...
Nuclide 3006.09c -- lithium 6 at 923K (Li-6)
Nuclide 3007.09c -- lithium 7 at 923K (Li-7)
Nuclide 4009.09c -- beryllium 9 at 923K (Be-9)
Nuclide 5010.09c -- boron 10 at 1073K (B-10)
Nuclide 5011.09c -- boron 11 at 1073K (B-11)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09c -- natural carbon at 923K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09c -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 923K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 923K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (6000.09c mt 2)
Nuclide 6000.09s -- natural carbon at 1073K (C-nat)
***** Fri Jun 12 17:46:59 2015 (seed = 1434156416)
Warning message from function ProcessMuDistributions:
1 coincident energy points in mubar data (8016.09c mt 2)
Nuclide 8016.09c -- oxygen 16 at 1073K (O-16)
Nuclide 9019.09c -- fluorine 19 at 923K (F-19)
Nuclide 12000.09c -- natural magnesium at 1073K (Mg-nat)
Nuclide 14000.09c -- natural silicon at 1073K (Si-nat)
Nuclide 92235.09c -- uranium 235 at 1073K (U-235)
Nuclide 92238.09c -- uranium 238 at 1073K (U-238)
SUMMARY -- 21 nuclides included in calculation:
- 21 transport nuclides
- Neutron energy cut-offs at 1.00E-11 and 20.0 MeV
- 588 transport reactions
- 105 special reactions
- 100.46 Mb of memory allocated for data
Normalizing compositions and processing mixtures...
OK.
Allocating memory for macroscopic cross section data...
OK.
Allocating memory for particle structures...
OK.
Calculating maximum densities...
OK.
Performing density cut-off...
OK.
Sorting material-wise reaction lists:
0% complete
8% complete
17% complete
25% complete
50% complete
100% complete
Calculating macroscopic cross sections:
0% complete
8% complete
17% complete
25% complete
33% complete
42% complete
50% complete
58% complete
67% complete
75% complete
83% complete
92% complete
100% complete
Calculating DT neutron majorant cross section:
0% complete
83% complete
100% complete
Clearing results and statistics...
OK.
Sampling initial source...
OK.
Inactive cycle 1 / 500: k-eff = 1.00000
Inactive cycle 2 / 500: k-eff = 1.20223
Inactive cycle 3 / 500: k-eff = 1.22492
Inactive cycle 4 / 500: k-eff = 1.23400
Inactive cycle 5 / 500: k-eff = 1.23868
Inactive cycle 6 / 500: k-eff = 1.24397
Inactive cycle 7 / 500: k-eff = 1.25010
Inactive cycle 8 / 500: k-eff = 1.24730
Inactive cycle 9 / 500: k-eff = 1.25254
Inactive cycle 10 / 500: k-eff = 1.25204
Inactive cycle 11 / 500: k-eff = 1.24983
Inactive cycle 12 / 500: k-eff = 1.24731
Inactive cycle 13 / 500: k-eff = 1.25028
Inactive cycle 14 / 500: k-eff = 1.24517
Inactive cycle 15 / 500: k-eff = 1.24700
Inactive cycle 16 / 500: k-eff = 1.25196
Inactive cycle 17 / 500: k-eff = 1.25388
Inactive cycle 18 / 500: k-eff = 1.24874
Inactive cycle 19 / 500: k-eff = 1.24941
Inactive cycle 20 / 500: k-eff = 1.25194
Inactive cycle 21 / 500: k-eff = 1.25319
Inactive cycle 22 / 500: k-eff = 1.25426
Inactive cycle 23 / 500: k-eff = 1.24424
Inactive cycle 24 / 500: k-eff = 1.24942
Inactive cycle 25 / 500: k-eff = 1.25010
Inactive cycle 26 / 500: k-eff = 1.25226
Inactive cycle 27 / 500: k-eff = 1.24708
Inactive cycle 28 / 500: k-eff = 1.24981
Inactive cycle 29 / 500: k-eff = 1.25007
Inactive cycle 30 / 500: k-eff = 1.25080
Inactive cycle 31 / 500: k-eff = 1.25136
Inactive cycle 32 / 500: k-eff = 1.25444
Inactive cycle 33 / 500: k-eff = 1.25125
Inactive cycle 34 / 500: k-eff = 1.25180
Inactive cycle 35 / 500: k-eff = 1.25284
Inactive cycle 36 / 500: k-eff = 1.25017
Inactive cycle 37 / 500: k-eff = 1.24851
Inactive cycle 38 / 500: k-eff = 1.25250
Inactive cycle 39 / 500: k-eff = 1.24755
Inactive cycle 40 / 500: k-eff = 1.24975
Inactive cycle 41 / 500: k-eff = 1.24642
Inactive cycle 42 / 500: k-eff = 1.25360