Bug in JEFF3.2 Am241 data
Posted: Wed Jun 21, 2017 10:50 am
I run FISPACT 3.20 with the following files:
files:
# gamma attenuation data
absorp /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/abs_2012
# index of nuclides to be included
ind_nuc /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32_decay12_index
# Library cross section data
xs_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32-n/gxs-709
# Library probability tables for self-shielding
prob_tab /home/mariusz/FISPACT-II-3-20/ENDFdata/TENDL2015data/tal2015-n/tp-709-294
#fluxes
fluxes fluxes
# Library decay data
dk_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/decay_2012
# Library fission data
fy_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32-n/jeff311nfy
# Library regulatory data
hazards /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/hazards_2012
clear /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/clear_2012
a2data /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/a2_2012
# collapsed cross section data (in and out)
collapxi COLLAPX1
collapxo COLLAPX1
# condensed decay and fission data (in and out)
arrayx ARRAYX1
…………………………………………………………………………………………………………………………………………….
fluxes:
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
(repeated 88 times)
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.5000E+13 0.0000E+00
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
(repeated 27 times)
0.0000E+00
1.00
MY SPECTRUM FOR THERMAL ENERGY
…………………………………………………………………………………………………………………………………………….
collapse.i:
<< -----collapse cross section data----- >>
CLOBBER
GETXS 1 709
FISPACT
* COLLAPSE jeff32-n/gxs-709 decay12 index
PRINTLIB 4
END
* END OF RUN
…………………………………………………………………………………………………………………………………………….
fisprun:
echo 'Running collapse with JEFF3.2 709-xs'
fispact collapse
…………………………………………………………………………………………………………………………………………….
The data for Am241 (n,g) in the collapse.out file was:
Am241 (n,g ) n 0m 6.91622E+01+- 0.00000E+00
It is probably the value for Am241 (n,g) Am242m, but the name of the result nuclide is corrupted. What is more important, there is no data for the Am241 (n,g) Am242 reaction where the xs should be ca 10 times larger.
The same runs done for ENDFB-7.1 and JENDL-4.0 libraries give the following results:
ENDF:
Am241 (n,g ) Am242m 6.77809E+01+- 5.00000E+00
Am241 (n,g ) Am242 6.10028E+02+- 5.00000E+00
JENDL:
Am241 (n,g ) Am242m 7.04921E+01+- 0.00000E+00
Am241 (n,g ) Am242 6.07317E+02+- 0.00000E+00
and these results are ok.
files:
# gamma attenuation data
absorp /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/abs_2012
# index of nuclides to be included
ind_nuc /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32_decay12_index
# Library cross section data
xs_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32-n/gxs-709
# Library probability tables for self-shielding
prob_tab /home/mariusz/FISPACT-II-3-20/ENDFdata/TENDL2015data/tal2015-n/tp-709-294
#fluxes
fluxes fluxes
# Library decay data
dk_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/decay_2012
# Library fission data
fy_endf /home/mariusz/FISPACT-II-3-20/ENDFdata/JEFF32data/jeff32-n/jeff311nfy
# Library regulatory data
hazards /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/hazards_2012
clear /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/clear_2012
a2data /home/mariusz/FISPACT-II-3-20/ENDFdata/decay/a2_2012
# collapsed cross section data (in and out)
collapxi COLLAPX1
collapxo COLLAPX1
# condensed decay and fission data (in and out)
arrayx ARRAYX1
…………………………………………………………………………………………………………………………………………….
fluxes:
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
(repeated 88 times)
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.5000E+13 0.0000E+00
0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00
(repeated 27 times)
0.0000E+00
1.00
MY SPECTRUM FOR THERMAL ENERGY
…………………………………………………………………………………………………………………………………………….
collapse.i:
<< -----collapse cross section data----- >>
CLOBBER
GETXS 1 709
FISPACT
* COLLAPSE jeff32-n/gxs-709 decay12 index
PRINTLIB 4
END
* END OF RUN
…………………………………………………………………………………………………………………………………………….
fisprun:
echo 'Running collapse with JEFF3.2 709-xs'
fispact collapse
…………………………………………………………………………………………………………………………………………….
The data for Am241 (n,g) in the collapse.out file was:
Am241 (n,g ) n 0m 6.91622E+01+- 0.00000E+00
It is probably the value for Am241 (n,g) Am242m, but the name of the result nuclide is corrupted. What is more important, there is no data for the Am241 (n,g) Am242 reaction where the xs should be ca 10 times larger.
The same runs done for ENDFB-7.1 and JENDL-4.0 libraries give the following results:
ENDF:
Am241 (n,g ) Am242m 6.77809E+01+- 5.00000E+00
Am241 (n,g ) Am242 6.10028E+02+- 5.00000E+00
JENDL:
Am241 (n,g ) Am242m 7.04921E+01+- 0.00000E+00
Am241 (n,g ) Am242 6.07317E+02+- 0.00000E+00
and these results are ok.