Default library ID

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michaelvmartin15
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Re: Default library ID

Post by michaelvmartin15 » Sat Mar 18, 2017 10:32 pm

Works perfectly.

Thank you.

andrewryh
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Re: Default library ID

Post by andrewryh » Wed Jul 18, 2018 4:31 pm

Hello everyone,

I had the same error when trying to deplete two materials:

Code: Select all

Adjusting nuclide  26056.09c temperature from 900K to 923K...

Checking data and printing output...

***** Wed Jul 18 08:08:35 2018:

 - MPI task         = 0
 - OpenMP thread    = 0
 - RNG parent seed  = 1531919224

Fatal error in function CheckNuclideData:

Duplicate found ZAI 20060 id = 09c T = 900.0T
I also use

Code: Select all

set printm 1 0.0
to generate *.bumat file, then making certain changes in mixtures and ran it again.

My materials file:

Code: Select all

mat  fuel  3.15810972515102E-02 fix 09c 900 burn 1 vol 3.04805E+04
            1001.09c  7.15221282395228E-09
            1002.09c  7.52506793952268E-11
            1003.09c  9.99103501793492E-13
            2003.09c  2.29845646812896E-15
            2004.09c  6.56005787160290E-09
               20060  1.37825885357368E-43
            3006.09c  6.13955156337441E-38
            3007.09c  8.99572740952298E-35
               30080  5.38514928077223E-41
               30090  1.98309015845704E-50
               40080  3.24194746820765E-59
            4009.09c  1.25703105942146E-32
               40100  2.63847821955548E-37
               40110  1.83898431296395E-41
              ..............................................................
mat  blank  3.15839393126892E-02 fix 09c 900 burn 1 vol 1.32630E+04
            1001.09c  1.47572046774792E-09
            1002.09c  1.63038523728714E-11
            1003.09c  2.36038294700319E-13
            2003.09c  5.42814875106739E-16
            2004.09c  1.10311225917136E-09
               20060  1.13180388633239E-46
            3006.09c  5.04649495186354E-41
            3007.09c  2.91647538673063E-37
               30080  1.74881393031211E-43
               30090  1.93301045431324E-53
               40080  2.33173146910818E-62
            4009.09c  4.12245545690506E-35
               40100  1.14163450565319E-39
               40110  6.08315247499870E-44
            5010.09c  6.73687839744390E-39
            5011.09c  7.35407203228358E-29
               50120  2.34532956881089E-35
              ..............................................................
If I try burnup only one material (keep burn 1 parameter for 1 mixture) - it does work.
Unfortunately, I cannot use binary restart files because I have to change mixture after each step.

Any help greatly appreciated.
Thanks.

Andrei

Ville Valtavirta
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Re: Default library ID

Post by Ville Valtavirta » Wed Jul 25, 2018 2:43 pm

What happens if you change the identifiers manually

Code: Select all

20060 -> 2006.09c
30080 -> 3008.09c
etc.
and run the calculation without the "fix" option in the material card?

-Ville

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Jaakko Leppänen
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Re: Default library ID

Post by Jaakko Leppänen » Thu Aug 30, 2018 11:34 am

I don't know what the exact cause of the problem is, but it looks like you have several nuclides with very low atomic density (~E-40). Have you tried setting the density criterion to some reasonable non-zero value (1E-15 or something like that) to get rid of these nuclides that seem to cause the problems?
- Jaakko

byba90
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Re: Default library ID

Post by byba90 » Sat Oct 20, 2018 6:39 pm

Dear all,

I had the same problem (version 2.1.29):

-I used fix <id> <T> for 5 burnup regions, getting the error message:

Code: Select all

 Fatal error in functionCheckNuclideData:

Duplicate found ZAI 20060 id = 09c T = 900.0T

In this case, the order of magnitude of the concentration for 20060 is E-16.

-I tried to change the identifiers manually, as suggested by Ville , but I get another error:

Code: Select all

Nuclide 2006.09c not found in data libraries
Anyone who solved the problem or other suggestions, please?

Thank you for your time.
Regards,

Christian

andrewryh
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Re: Default library ID

Post by andrewryh » Thu Oct 25, 2018 5:38 pm

Ville Valtavirta wrote:What happens if you change the identifiers manually

Code: Select all

20060 -> 2006.09c
30080 -> 3008.09c
etc.
and run the calculation without the "fix" option in the material card?

-Ville
Jaakko Leppänen wrote: I don't know what the exact cause of the problem is, but it looks like you have several nuclides with very low atomic density (~E-40). Have you tried setting the density criterion to some reasonable non-zero value (1E-15 or something like that) to get rid of these nuclides that seem to cause the problems?
I tried both options - and got the same issues as byba90.

Any suggestions on how to fix it, please?

Thanks.
Andrei

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Jaakko Leppänen
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Re: Default library ID

Post by Jaakko Leppänen » Fri Oct 26, 2018 11:58 am

Can you post or send me the full input by e-mail?
- Jaakko

byba90
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Re: Default library ID

Post by byba90 » Sat Oct 27, 2018 6:31 pm

Ok Jaakko, thank you very much. I sent an email, so I also provided you the bumat file, very long to post.
Regards,

Christian

andrewryh
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Re: Default library ID

Post by andrewryh » Wed Oct 31, 2018 1:11 am

Jaakko Leppänen wrote:Can you post or send me the full input by e-mail?
Hello, Jaakko. Thank for the answer.

My main input file:

Code: Select all

include "bumat1"
include "../../unit_cell.inp"
% --- Hastelloy N
mat hast     -8.671 rgb 127 205 187 burn 1   % Structural material T assumed=blanket T
28000.09c    -72.0      % Mass fraction of Ni
42000.09c    -16.0      % Mass fraction of Mo
24000.09c    -7.0       % Mass fraction of Cr
26000.09c    -5.0       % Mass fraction of Fe
% ----- Boundary conditions
set bc 3		% Periodic BC

% +++ Run parameters +++ %
% ---- Libraries
set acelib "/home/andrei2/serpent/xsdata/endfb7/sss_endfb7.xsdata" 
set declib "/home/andrei2/serpent/xsdata/endfb7/sss_endfb7.dec"      
set nfylib "/home/andrei2/serpent/xsdata/endfb7/sss_endfb7.nfy"       

% --- Neutron population
set pop 10000 150 50
% --- Depletion parameters
% --- Options for burnup calculation:
set bumode  2  % CRAM method
set pcc     1  % Predictor-corrector calculation on
set opti 3

% --- Irradiation cycle:
set powdens 30.7062436E-3

dep
daytot 30
set printm 1 0.0
My geometry file unit_cell.inp:

Code: Select all

surf 101 cyl 0.0 0.0 98.50			% Core (fuel salt)    87.67
surf 103 cyl 0.0 0.0 118.00			% Fertile salt        93.37
surf 104 sqc 0.0 0.0 118.00			% Fertile salt

cell 1001 0 fuel	-101			% Core
cell 1003 0 blank	-103 101		% Blanket
cell 1004 0 hast	-104 103		% THermal insulation/reflector
cell 1099 0 outside	104			% Outside world

andrewryh
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Re: Default library ID

Post by andrewryh » Wed Oct 31, 2018 1:14 am

And my bumat file which I took from the previous run and add fix 09c 900 burn 1 (I have cut it to post here but even cutted version still cause the problem):

Code: Select all


% Material compositions (0.92 MWd/kgU / 30.00 days)

% Decay isotopes with afrac >= 0.00000E+00 included

mat  fuel  3.15810969282600E-02 fix 09c 900 burn 1 vol 3.04805E+04
            1001.09c  7.19548998617004E-09
            1002.09c  7.65411073418352E-11
            1003.09c  1.01148548172494E-12
            2003.09c  2.32693117726566E-15
            2004.09c  6.59608030324828E-09
               20060  1.09137089817044E-43
            3006.09c  4.86148835993620E-38
            3007.09c  9.66830520356072E-35
               30080  5.82100233147657E-41
               30090  1.65728328979095E-50
               40080  2.57068816593885E-59
            4009.09c  9.96490332491812E-33
               40100  2.83247829875581E-37
               40110  1.97954288712383E-41
            5010.09c  1.93653148226588E-36
            5011.09c  5.05475997219618E-27
               50120  2.07561150964106E-33
            6012.09c  6.17325933162401E-26
               60130  1.53323101572601E-26
               60140  5.89931332522558E-26
               60150  4.96614960160059E-32
               70130  4.70270364108474E-39
            7014.09c  2.17340633560210E-26
            7015.09c  6.09167648783599E-18
               70160  1.04578473900919E-25
               70170  9.11543885491215E-38
               80150  1.09181865819244E-36
            8016.09c  8.80759252373914E-21
            8017.09c  5.49015524229666E-24

mat  blank  3.15839402871430E-02 fix 09c 900 burn 1 vol 1.32630E+04
            1001.09c  1.50131749014371E-09
            1002.09c  1.63481763055884E-11
            1003.09c  2.12643763468479E-13
            2003.09c  4.89003154129187E-16
            2004.09c  1.11920764634903E-09
               20060  7.41812463256977E-47
            3006.09c  3.30761298882003E-41
            3007.09c  1.80916778119507E-37
               30080  1.04562843668792E-43
               30090  9.01161798316518E-54
               40080  1.54586989425452E-62
            4009.09c  2.69243778500419E-35
               40100  4.67209840454101E-40
               40110  3.67097179573277E-44
            5010.09c  3.38723463840767E-39
            5011.09c  4.26918778981434E-29
               50120  1.91853497397193E-35
            6012.09c  5.71572504403145E-28
               60130  1.09549908919033E-28
               60140  5.41329427825865E-28
               60150  4.64931825712826E-34
               70130  9.53597902852316E-42
            7014.09c  2.02525174259253E-28
            7015.09c  2.60821791242957E-19
               70160  2.36533749729583E-27
               70170  4.59084036822785E-40
               80150  4.92197107402220E-39
            8016.09c  1.99590636705379E-22
            8017.09c  1.27486643164841E-25
               80180  1.07524076860817E-21
               80190  6.35218346948075E-28
               90180  7.83234342824761E-24
            9019.09c  4.44642633946072E-16
               90200  2.53237936986490E-15
              100200  4.10998564644788E-10
              100210  8.61531735336856E-15
              100220  1.16656937789808E-13
              100230  1.77629206984293E-14
              110210  3.78840278416950E-26
           11022.09c  4.19774916910165E-12
           11023.09c  6.76792711124989E-03
              110240  1.20456240425056E-09
              110241  3.47139133465680E-16
              110250  5.44406557989399E-25
              110260  4.61642609684308E-34
              120230  2.10923805017345E-24
           12024.09c  3.89977837591939E-08
           12025.09c  1.15740847723356E-13
           12026.09c  3.53876480815841E-19
              120270  4.50593418683586E-27
              130260  2.05121805591147E-34
           13027.09c  3.69917226695827E-24
              130280  1.25881413151915E-27
              130290  7.13699188356504E-30
              130300  6.07378921746229E-30
              140270  7.86637489535815E-42
           14028.09c  5.57590988966298E-24
           14029.09c  1.69753100229268E-20
           14030.09c  1.13206192366002E-15
Thank you very much for help!

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