Fatal error in function SumPrivateData:Pointer error.

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nico
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Fatal error in function SumPrivateData:Pointer error.

Post by nico » Wed Feb 28, 2018 2:42 pm

Dear all,

I updated Serpent to version 2.1.30, and I notice an error message that did not appear when running the very same input file with the previous code version (2.1.29). I ran the input in OpenMP mode with -omp 8.
Specifically, the error message I get is:

Code: Select all

***** Wed Feb 28 10:08:57 2018:

 - MPI task         = 0
 - OpenMP thread    = 0
 - RNG parent seed  = 1519808933
 - RNG history seed = 4820742361103036837
 - RNG history idx  = 1997

Fatal error in function SumPrivateData:

Pointer error

Simulation aborted.
This error comes up as soon as the 2nd inactive cycle is completed, interrupting the calculation.

I attach both the full output log and the input file. Be careful: the file to run is named 'MSFR', but path directories have to be changed in 'solid1_msfr' and 'MSFR' files.
Thanks a lot for the help

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Jaakko Leppänen
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Re: Fatal error in function SumPrivateData:Pointer error.

Post by Jaakko Leppänen » Thu Mar 01, 2018 2:15 pm

I don't see the attachment. Could you post the input in a text box instead?
- Jaakko

nico
Posts: 12
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Re: Fatal error in function SumPrivateData:Pointer error.

Post by nico » Thu Mar 01, 2018 3:46 pm

I am very sorry, it seemed to me that it was attached. Here is the input file that I would like to run, while in the zip there are the other files defining the materials and the stl files:

Code: Select all

% --- Box containing MSFR

surf 1 cyl 0.0 0.0 250.0 -280 280

% --- Definition of universes 

cell 1 0 fill 1  -22             % core universe (2# surfaces are defined in background_msfr)
cell 3 0 fill 1   22 -1  26      % hot leg universe
cell 4 0 fill 1   22 -1 -28      % cold leg universe
cell 5 0 fill 3   22 -1 -26  28  % HX universe
cell 6 0 outside  1

% --- External file inclusion

include "/home/abrate/serpent/msfr/background_MSFR"  % background universe
include "/home/abrate/serpent/msfr/solids1_MSFR"     % solid card for stl files
include "/home/abrate/serpent/msfr/materials_MSFR"   % materials definition

% --- Nuclear data library setting

set acelib "/opt/serpent/xsdata/jeff311/sss_jeff311.xsdata" % Script from Milan uses jeff311u;

% --- Run & plot parameters:

set his 1

set impl 0 1 1 % WATCH OUT : not clear why this option is used

set nfg 6 [7.48518E-04 5.53084E-03 2.47875E-02 4.97871E-01 2.23130E+00]  % 6 groups definition (to be confermed)

%% set nfg 9 [1.290E-05 3.325E-05 5.200E-05 1.860E-04 2.290E-03 7.300E-02 5.730E-1 1.400E+00]  % suddivisione 9 gruppi

set gcu 1 3 21 22 23 24       % 1=core+legs, 3=HX, 21=top refl, 22= bottom refl, 23=fertile, 24=b4c


plot 1 1000 1000 [27 -300 300 -180 180]
plot 2 1000 1000 [27 0 300 -180 180]
plot 3 1000 1000 [0 -300 300 -300 300]
plot 3 1000 1000 [120 -300 300 -300 300]
plot 3 1000 1000 [109 -300 300 -300 300]


% --- Statistics parameters

set pop 10000 1000 300

% --- Define the energy grid to be used with the detector
%     Grid type 3 (bins have uniform lethargy width)
%     500 bins between 1e-11 MeV and 2e1 MeV.

ene ene_grid 3 1000 1e-10 2e1

% --- Detector for tallying the flux energy spectrum
%     The energy grid used for tallying will be defined later

%det energy dc 1 de ene_grid

det fuel_fiss   dr -6  fuel    dm fuel     de ene_grid %dn 1 0.0 90 20 0 360 1 -90 90 10

det blank_fiss  dr -2  fertile dm fertile  de ene_grid


% --- Fission rate detector

det tot_fission dr  -6 void % dr is the response, void means that each materials at interaction point is considered;

% Fission rate mesh plot:

mesh 8 4 fuel_fiss 1 1030 1315
mesh 8 4 fuel_fiss 2 1330 1315
mesh 8 4 fuel_fiss 3 1315 1315

mesh 8 4 blank_fiss 1 1030 1315
mesh 8 4 blank_fiss 2 1330 1315
mesh 8 4 blank_fiss 3 1315 1315


% --- XZ-meshplot (2)

mesh 2 1000 1000

% --- XY-meshplot (3)

mesh 3 1000 1000

This code currenly runs without any problem on version 2.1.29 but generates this error when compiled on another machine with 2.1.30:

Code: Select all

abrate@vpcen13:~/serpent/msfr_serp$ sss2 -omp 8 MSFR

  _                   .-=-.           .-=-.          .-==-.
 { }      __        .' 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 2.1.30 (February 14, 2018) -- Contact: serpent@vtt.fi

 - Reference: J. Leppanen, et al. "The Serpent Monte Carlo code: Status,
              development and applications in 2013." Ann. Nucl. Energy,
              82 (2015) 142-150.

 - Compiled Feb 27 2018 16:25:38

 - MPI Parallel calculation mode not available

 - OpenMP Parallel calculation mode available

 - Geometry and mesh plotting available

 - Default data path not set

Begin calculation on Wed Feb 28 10:08:53 2018

Reading input file "MSFR"...
Reading input file "/home/abrate/serpent/msfr_serp/background_MSFR"...
Reading input file "/home/abrate/serpent/msfr_serp/solids1_MSFR"...
Reading input file "/home/abrate/serpent/msfr_serp/materials_MSFR"...

Reading stereolithography (STL) geometries...
OK.

Checking duplicate input definitions...
OK.

Creating geometry...
OK.

Counting geometry zones...

The geometry consists of 4 levels:

Level 0 size: max 5 zones
Level 1 size: max 34 zones
Level 2 size: max 15 zones
Level 3 size: max 1 zones

Processing cells...
OK.

Processing STL geometry in universe 1:

STL body "fuel" :

 - Cell: "fuel"
 - Material: "fuel"
 - 1 components
 - 2108 triangular facets
 - 1056 (unique) points

STL body "cold1" :

 - Cell: "cold1"
 - Material: "cold"
 - 1 components
 - 486 triangular facets
 - 243 (unique) points

STL body "cold2" :

 - Cell: "cold2"
 - Material: "cold"
 - 1 components
 - 474 triangular facets
 - 237 (unique) points

STL body "cold3" :

 - Cell: "cold3"
 - Material: "cold"
 - 1 components
 - 482 triangular facets
 - 241 (unique) points

STL body "cold4" :

 - Cell: "cold4"
 - Material: "cold"
 - 1 components
 - 494 triangular facets
 - 247 (unique) points

STL body "cold5" :

 - Cell: "cold5"
 - Material: "cold"
 - 1 components
 - 486 triangular facets
 - 243 (unique) points

STL body "cold6" :

 - Cell: "cold6"
 - Material: "cold"
 - 1 components
 - 474 triangular facets
 - 237 (unique) points

STL body "cold7" :

 - Cell: "cold7"
 - Material: "cold"
 - 1 components
 - 482 triangular facets
 - 241 (unique) points

STL body "cold8" :

 - Cell: "cold8"
 - Material: "cold"
 - 1 components
 - 494 triangular facets
 - 247 (unique) points

STL body "cold9" :

 - Cell: "cold9"
 - Material: "cold"
 - 1 components
 - 486 triangular facets
 - 243 (unique) points

STL body "cold10" :

 - Cell: "cold10"
 - Material: "cold"
 - 1 components
 - 474 triangular facets
 - 237 (unique) points

STL body "cold11" :

 - Cell: "cold11"
 - Material: "cold"
 - 1 components
 - 482 triangular facets
 - 241 (unique) points

STL body "cold12" :

 - Cell: "cold12"
 - Material: "cold"
 - 1 components
 - 494 triangular facets
 - 247 (unique) points

STL body "cold13" :

 - Cell: "cold13"
 - Material: "cold"
 - 1 components
 - 486 triangular facets
 - 243 (unique) points

STL body "cold14" :

 - Cell: "cold14"
 - Material: "cold"
 - 1 components
 - 474 triangular facets
 - 237 (unique) points

STL body "cold15" :

 - Cell: "cold15"
 - Material: "cold"
 - 1 components
 - 482 triangular facets
 - 241 (unique) points

STL body "cold16" :

 - Cell: "cold16"
 - Material: "cold"
 - 1 components
 - 494 triangular facets
 - 245 (unique) points

STL body "hot1" :

 - Cell: "hot1"
 - Material: "hot"
 - 1 components
 - 278 triangular facets
 - 139 (unique) points

STL body "hot2" :

 - Cell: "hot2"
 - Material: "hot"
 - 1 components
 - 266 triangular facets
 - 133 (unique) points

STL body "hot3" :

 - Cell: "hot3"
 - Material: "hot"
 - 1 components
 - 274 triangular facets
 - 137 (unique) points

STL body "hot4" :

 - Cell: "hot4"
 - Material: "hot"
 - 1 components
 - 286 triangular facets
 - 143 (unique) points

STL body "hot5" :

 - Cell: "hot5"
 - Material: "hot"
 - 1 components
 - 278 triangular facets
 - 139 (unique) points

STL body "hot6" :

 - Cell: "hot6"
 - Material: "hot"
 - 1 components
 - 266 triangular facets
 - 133 (unique) points

STL body "hot7" :

 - Cell: "hot7"
 - Material: "hot"
 - 1 components
 - 274 triangular facets
 - 137 (unique) points

STL body "hot8" :

 - Cell: "hot8"
 - Material: "hot"
 - 1 components
 - 286 triangular facets
 - 143 (unique) points

STL body "hot9" :

 - Cell: "hot9"
 - Material: "hot"
 - 1 components
 - 278 triangular facets
 - 139 (unique) points

STL body "hot10" :

 - Cell: "hot10"
 - Material: "hot"
 - 1 components
 - 266 triangular facets
 - 133 (unique) points

STL body "hot11" :

 - Cell: "hot11"
 - Material: "hot"
 - 1 components
 - 274 triangular facets
 - 137 (unique) points

STL body "hot12" :

 - Cell: "hot12"
 - Material: "hot"
 - 1 components
 - 286 triangular facets
 - 143 (unique) points

STL body "hot13" :

 - Cell: "hot13"
 - Material: "hot"
 - 1 components
 - 278 triangular facets
 - 139 (unique) points

STL body "hot14" :

 - Cell: "hot14"
 - Material: "hot"
 - 1 components
 - 266 triangular facets
 - 133 (unique) points

STL body "hot15" :

 - Cell: "hot15"
 - Material: "hot"
 - 1 components
 - 274 triangular facets
 - 137 (unique) points

STL body "hot16" :

 - Cell: "hot16"
 - Material: "hot"
 - 1 components
 - 286 triangular facets
 - 141 (unique) points

Filling empty search mesh cells...
OK.

Adaptive search mesh:

 - Dimensions: x = [-200.9, 200.9]; y = [-200.9, 200.9]; z = [-123.9, 123.9]
 - Depth: 5 4 3 2
 - 371373 mesh cells
 - 87.3% of volume consists of pre-assigned data
 - 62.37 Mb of memory allocated for search mesh

Processing STL geometry in universe 3:

STL body "heat1" :

 - Cell: "heat1"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat2" :

 - Cell: "heat2"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat3" :

 - Cell: "heat3"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat4" :

 - Cell: "heat4"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat5" :

 - Cell: "heat5"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat6" :

 - Cell: "heat6"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat7" :

 - Cell: "heat7"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat8" :

 - Cell: "heat8"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat9" :

 - Cell: "heat9"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat10" :

 - Cell: "heat10"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat11" :

 - Cell: "heat11"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat12" :

 - Cell: "heat12"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat13" :

 - Cell: "heat13"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat14" :

 - Cell: "heat14"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat15" :

 - Cell: "heat15"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

STL body "heat16" :

 - Cell: "heat16"
 - Material: "heat"
 - 1 components
 - 12 triangular facets
 - 8 (unique) points

Filling empty search mesh cells...
OK.

Adaptive search mesh:

 - Dimensions: x = [-221.2, 221.2]; y = [-221.2, 221.2]; z = [-83.5, 83.5]
 - Depth: 5 4 3 2
 - 596529 mesh cells
 - 86.5% of volume consists of pre-assigned data
 - 77.01 Mb of memory allocated for search mesh

OK.

Linking materials to geometry...
OK.

Counting cells...
OK.

Processing data for group constant generation:

 - 70 energy groups in micro-group structure
 - 6 energy groups in macro-group structure
 - B1 fundamental mode calculation is not run
 - Group constants generated in 6 universes
 - Discontinuity factors are not calculated
 - Pin-power distributions are not calculated
 - Albedos are not calculated
 - Poison cross sections are not calculated

Reading ACE directory files...
OK.

Adding nuclides in material fuel...

Nuclide   3007.09c -- lithium 7 at 900K (Li-7)
Nuclide   9019.09c -- fluorine 19 at 900K (F-19)
Nuclide  90232.09c -- thorium 232 at 900K (Th-232)
Nuclide  92233.09c -- uranium 233 at 900K (U-233)

Adding nuclides in material heat...

Nuclide  28000.09c -- natural nickel at 900K (Ni-nat)
Nuclide  74000.09c -- natural tungsten at 900K (W-nat)
Nuclide  24000.09c -- natural chromium at 900K (Cr-nat)
Nuclide  13027.09c -- aluminum 27 at 900K (Al-27)

Adding nuclides in material cold...

Adding nuclides in material hot...

Adding nuclides in material b4c...

Nuclide   5010.09c -- boron 10 at 900K (B-10)
Nuclide   5011.09c -- boron 11 at 900K (B-11)
Nuclide   6000.09c -- natural carbon at 900K (C-nat)

Adding nuclides in material fertile...

Adding nuclides in material air...

Nuclide   2004.03c -- helium 4 at 300K (He-4)

Adding nuclides in material steelTop...

Nuclide  26000.09c -- natural iron at 900K (Fe-nat)

Adding nuclides in material steelBottom...

Checking data and printing output...
OK.


***** Wed Feb 28 10:08:56 2018 (seed = 1519808933)
Warning message from function ProcessNuclides:

Minimum photon cross section energy 1.000000E+37 MeV is
above the energy grid minimum 1.000000E-03 MeV.
The energy grid minimum is set to 1.000000E+37 MeV.
Possible changes in energy cutoff cards (warned if any).


***** Wed Feb 28 10:08:56 2018 (seed = 1519808933)
Warning message from function ProcessNuclides:

Photon energy cutoff 1.000000E-03 MeV is changed to 1.000000E+37.


Generating unionize energy grids...

Adding points:

  2004.03c -- Points added in neutron grid: 534
  3007.09c -- Points added in neutron grid: 76
  5010.09c -- Points added in neutron grid: 182
  5011.09c -- Points added in neutron grid: 2568
  6000.09c -- Points added in neutron grid: 587
  9019.09c -- Points added in neutron grid: 1076
 13027.09c -- Points added in neutron grid: 2017
 24000.09c -- Points added in neutron grid: 5430
 26000.09c -- Points added in neutron grid: 10987
 28000.09c -- Points added in neutron grid: 19217
 74000.09c -- Points added in neutron grid: 9925
 90232.09c -- Points added in neutron grid: 17027
 92233.09c -- Points added in neutron grid: 2630

Generating unionized energy grid:

 - Unionization performed without grid thinning
   between 1.00E-11 and 20.0 MeV.

 - Final neutron grid size: 72131 points.

 - 2.42 Mb of memory allocated for grid data

OK.

Processing cross sections and ENDF reaction laws...

Nuclide   2004.03c -- helium 4 at 300K (He-4)
Nuclide   3007.09c -- lithium 7 at 900K (Li-7)
Nuclide   5010.09c -- boron 10 at 900K (B-10)
Nuclide   5011.09c -- boron 11 at 900K (B-11)
Nuclide   6000.09c -- natural carbon at 900K (C-nat)
Nuclide   9019.09c -- fluorine 19 at 900K (F-19)
Nuclide  13027.09c -- aluminum 27 at 900K (Al-27)
Nuclide  24000.09c -- natural chromium at 900K (Cr-nat)
Nuclide  26000.09c -- natural iron at 900K (Fe-nat)
Nuclide  28000.09c -- natural nickel at 900K (Ni-nat)
Nuclide  74000.09c -- natural tungsten at 900K (W-nat)
Nuclide  90232.09c -- thorium 232 at 900K (Th-232)
Nuclide  92233.09c -- uranium 233 at 900K (U-233)

SUMMARY -- 13 nuclides included in calculation:

 - 13 transport nuclides
 - Neutron energy cut-offs at 1.00E-11 and 20.0 MeV
 - 442 transport reactions
 - 129 special reactions
 - 72.66 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
 100% complete

Calculating macroscopic cross sections:

   0% complete
  89% complete
 100% complete

Calculating DT neutron majorant cross section:

   0% complete
  89% complete
 100% complete

Clearing results and statistics...
OK.

Sampling initial source...
OK.

Inactive cycle   1 / 150: k-eff = 1.00000
Inactive cycle   2 / 150: k-eff = 0.68900

***** Wed Feb 28 10:08:57 2018:

 - MPI task         = 0
 - OpenMP thread    = 0
 - RNG parent seed  = 1519808933
 - RNG history seed = 4820742361103036837
 - RNG history idx  = 1997

Fatal error in function SumPrivateData:

Pointer error

Simulation aborted.
Attachments
msfr_serp.7z
collection of input and stl files
(183.44 KiB) Downloaded 52 times

Ville Valtavirta
Posts: 417
Joined: Fri Sep 07, 2012 1:43 pm
Security question 1: No
Security question 2: 92

Re: Fatal error in function SumPrivateData:Pointer error.

Post by Ville Valtavirta » Thu Mar 01, 2018 5:12 pm

If there is an STL-model involved, the bug might be connected to the one reported in this post: http://ttuki.vtt.fi/serpent/viewtopic.p ... 2839#p8404

You could try the fix for addsearchmesh.c and see if that helps.

-Ville

nico
Posts: 12
Joined: Wed Feb 28, 2018 1:57 pm
Security question 1: No
Security question 2: 93

Re: Fatal error in function SumPrivateData:Pointer error.

Post by nico » Mon Mar 05, 2018 6:46 pm

The error was fixed editing the 'addsearchmesh.c' script as illustrated in the link!
Thank you so much

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