decay isotopes burnup never included?

Report all good and bad behavior here
Post Reply
Peter Wolniewicz
Posts: 135
Joined: Mon Dec 13, 2010 5:50 pm

decay isotopes burnup never included?

Post by Peter Wolniewicz » Thu Jan 07, 2016 11:10 pm

Im trying to figure out how to include decay isotopes.

I always get this message in the bumat output .txt file:

% Material compositions (0.00 MWd/kgU / 200.00 days)

% Decay isotopes not included


Ive tried uncommenting the inventory option below in my input file:

% burnstuff
%set fpcut 1e-20
%set inventory 204 201 202 208
set power 300
dep daytot
50
100
%set powdens 0
dep dectot
150
200
set printm 1


mat fuel11 -10.50 rgb 255 255 0 burn 1
92235.70c 0.016


The dep.m file never shows any nuclides at all (which I thought it should do when reading previous post on similar issues).

Best regards,

Peter :)

jesse.johns
Posts: 114
Joined: Wed Apr 20, 2011 5:19 am

Re: decay isotopes burnup never included?

Post by jesse.johns » Fri Jan 08, 2016 12:19 am

Hi Peter,

I recall this happening to me before. I don't recall what is it, but there might be a few things to check in the preliminary:

Did you set (this is my hunch):

Code: Select all

set declib "/dir/to/sss_endfb7.dec"
set nfylib "/dir/to/sss_endfb7.nfy"
Have you confirmed that there are fissions occurring within the burnable region?

Have you tried other inventory options? Such as just:

Code: Select all

set inventory
922350
Also, what is your code version?

Best,

Jesse

Peter Wolniewicz
Posts: 135
Joined: Mon Dec 13, 2010 5:50 pm

Re: decay isotopes burnup never included?

Post by Peter Wolniewicz » Fri Jan 08, 2016 1:35 pm

Fission are happening.
When I include 922350 (what does the extra zero mean?) the dep.m file looks like this in the beginning:

ZAI = [
922350
666
0
];

NAMES = [
'U235 '
'lost '
'total '
];

i922350 = 1; iU235 = 1;
iLOST = 2;
iTOT = 3;

MAT_fuel11_VOLUME = [ 1.30567E+04 1.30567E+04 1.30567E+04 1.30567E+04 1.30567E+04 ];

MAT_fuel11_BURNUP = [ 0.00000E+00 9.67915E-05 1.93843E-04 2.90895E-04 3.87946E-04 ];

MAT_fuel11_ADENS = [
2.69020E-02 2.69020E-02 2.69020E-02 2.69020E-02 2.69020E-02 % U235
0.00000E+00 2.12597E-17 4.23590E-17 4.23590E-17 4.23590E-17 % lost data
2.69020E-02 2.69020E-02 2.69020E-02 2.69020E-02 2.69020E-02 % total
];




I use the following xs / decay libraries:
set acelib "/home/peter/work/MY_MCNP/MCNP_DATA/sss_MCNP.xsdata"
set declib "/home/peter/work/_Serpent/_extralibs/unix/endf-b-vi-8_decay.dat"
set nfylib "/home/peter/work/_Serpent/_extralibs/unix/endf-b-vi-8_nfpy.dat"
set sfylib "/home/peter/work/_Serpent/_extralibs/unix/endf-b-vi-8_sfpy.dat"

The first lines in the decay library I use looks like this:

Retrieved by E4-util: 2007/04/12,11:45:06 1 0 0 0
1.003000+3 2.974228+0 -1 0 0 1 131 1451 1
0.000000+0 1.000000+0 0 0 0 6 131 1451 2
0.000000+0 0.000000+0 1 0 4 6 131 1451 3
0.000000+0 0.000000+0 0 0 8 2 131 1451 4
1-H - 3 INEL EVAL-FEB88 C.W.REICH 131 1451 5
DIST-SEP91 19910611 131 1451 6
----ENDF/B-VI MATERIAL 131 131 1451 7
-----RADIOACTIVE DECAY DATA 131 1451 8
------ENDF-6 FORMAT 131 1451 9
3H B- DECAY ENSDF DATED 870312 131 1451 10
Q-BETA: A. H. WAPSTRA AND G. AUDI, NUCL. PHYS. A432, 1 (1985). 131 1451 11
translated by Fred Mann (WHC) 131 1451 12
1 451 14 1 131 1451 13
8 457 9 1 131 1451 14
0.000000+0 0.000000+0 0 0 0 0 131 1 099999
0.000000+0 0.000000+0 0 0 0 0 131 0 0 0
1.003000+3 2.974228+0 0 0 0 1 131 8457 1
3.890969+8 1.893416+6 0 0 6 0 131 8457 2
5.690000+3 1.000000+1 0.000000+0 0.000000+0 0.000000+0 0.000000+0 131 8457 3
5.000000-1 1.000000+0 0 0 6 1 131 8457 4
1.000000+0 0.000000+0 1.859400+4 8.000000+0 1.000000+0 0.000000+0 131 8457 5
0.000000+0 1.000000+0 0 0 6 1 131 8457 6




I use serpent 2.1.23.

Are the libraries you use (decay and (n,f) ) available online through immediate download just like the endf ones I use are?

Best regards,

Peter

User avatar
Tuomas Viitanen
Posts: 65
Joined: Thu Mar 25, 2010 1:50 pm
Security question 2: 0
Location: VTT Technical Research Centre of Finland, Espoo

Re: decay isotopes burnup never included?

Post by Tuomas Viitanen » Fri Jan 08, 2016 2:15 pm

Hi,

The decay isotopes (i.e. nuclides without xs data) are not normally included in the .bumat output that you get with "set printm 1". The decay nuclides can be added in the bumat output using

set printm 1 <threshold>

where <threshold> is the threshold atomic fraction above which decay nuclides are included in the bumat output. "set printm 1 0.0" should, thus, include all nuclides in bumat output. This property should work at least with Serpent 2.1.24.

When it comes to the _dep output, only "inventory" nuclides are printed there. You can add all nuclides (including decay nuclides) in the inventory with "set inventory all".

Best regards,

Tuomas

jesse.johns
Posts: 114
Joined: Wed Apr 20, 2011 5:19 am

Re: decay isotopes burnup never included?

Post by jesse.johns » Tue Jan 12, 2016 6:42 am

what does the extra zero mean?
It allows you to specify the metastable states. Zero means the ground state.

I think the general problem then is how your specify the inventory. Looks like you found that thread. :-)

Post Reply