5.1.9.1. PRISM
Warning
PRISM is deprecated and replaced by Sampler (see Sect. 6.4 for details).
PRISM is a utility that reads a single input template file containing generic parameter flags and replaces them with specific values designated by the user to generate any number of files containing desired combinations of specific parameter values. PRISM provides a procedure to convert a generic input file for a particular fuel assembly design into a large number of input files containing combinations of specific fuel enrichment and moderator densities and/or other parameters for generating basic cross-section libraries. The program was designed in a general manner so PRISM can be used to generate multiple files from any generic file.
The input description for PRISM is presented in Table 5.B.1. The input format is free form. The user input includes the name of the template file to be read; the pattern for the name of the output files to be generated, using the generic parameter flags; the number of generic parameter flags; the number of files to be generated; each generic parameter flag and the specific values to be substituted in each output file.
The template file contains generic parameter flags. PRISM creates copies of the template file and substitutes specific values for the generic flags. Note that the character length of each specific value must be the same as that of the associated generic flag.
An example using PRISM to generate input files for six fuel enrichments is presented in Example 5.1.42 and Example 5.1.43. In this example a TRITON input file for a Westinghouse 17 \(\times\) 17 fuel assembly (Example 5.1.43) is processed by PRISM using the input file for PRISM listed in Example 5.1.42. The case generates 6 specific input files from the template file.
Line No. |
Parameter |
Description |
Comments |
1 |
TEMPLATE |
Template file name |
80 characters maximum |
2 |
OUT_TEMPLATE |
Pattern for output file names |
80 characters maximum Must contain enough generic parameter names to create unique filename for each output file |
3 |
NUMPARMS |
Number of generic parameter types |
|
NUMFILES |
Number of output files to be generated |
||
NOTE: Repeat the following data for each generic parameter type (i.e. a total of NUMPARMS times). |
|||
4 |
PARAM_NAME |
Generic parameter name as it appears in template file |
80 characters maximum |
5 1 |
PARAMETERS |
Specific values of generic parameter for each output file |
NUMFILES entries required. Length of value must be same as length of PARAM_NAME |
- 1
May be continued on subsequent lines as needed.
=shell
cp $RTNDIR/w17x17_template.input .
end
=prism
w17x17_template.input
w17_u235.inp
5 6
u234wt%
0.01200 0.01639 0.02543 0.03473 0.04423 0.05389
u235
1.50 2.00 3.00 4.00 5.00 6.00
u236wt%
0.00690 0.00920 0.01380 0.01840 0.02300 0.02760
u238wt%
98.4811 97.9744 96.9608 95.9469 94.9328 93.9185
namelibrary
w17_e15.lib
w17_e20.lib
w17_e30.lib
w17_e40.lib
w17_e50.lib
w17_e60.lib
end
=shell
cp w17*.inp $RTNDIR
end
=t-depl
PWR Westinghouse 17x17, 1/4 assembly model
44groupndf5
' ----------------------------------------------------------------
' template to generate libraries for ORIGEN-S
' parameters are: u235 - wt% U-235
' u234wt% - wt% U-234
' u236wt% - wt% U-236
' u238wt% - wt% U-238
' namelibrary - name of ORIGEN library created
' ----------------------------------------------------------------
' Mixture data
' ----------------------------------------------------------------
read comp
' fuel
uo2 1 den=10.412 1 900 92234 u234wt%
92235 u235
92236 u236wt%
92238 u238wt% end
'
' clad
zirc4 2 1 622 end
' water moderator with 630 ppm B
h2o 3 den=0.723 1 575.5 end
Figure .. Generic TRITON input template for PRISM.
arbmb 0.723 1 1 0 0 5000 100 3 630e-06 575.5 end
' gap
n 4 den=0.00125 1 622 end
' guide tube
zirc4 5 1 575.5 end
'
end comp
' ----------------------------------------------------------------
' Cell data
' ----------------------------------------------------------------
read celldata
latticecell squarepitch pitch=1.259 3
fueld=0.805 1
gapd=0.822 4
cladd=0.95 2
end
end celldata
' ----------------------------------------------------------------
' Depletion data
' ----------------------------------------------------------------
read depletion
1
end depletion
' ----------------------------------------------------------------
' Burn data
' ----------------------------------------------------------------
read burndata
power=40.0 burn=1e-15 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
power=40.0 burn=75 down=0 end
end burndata
' ----------------------------------------------------------------
' NEWT model data
' ----------------------------------------------------------------
read model
Westinghouse 17x17
read parm
cmfd=yes xycmfd=4
run=yes echo=yes drawit=no
end parm
read materials
1 1 ! fuel ! end
2 1 ! clad ! end
3 2 ! water ! end
4 0 ! gap ! end
5 1 ! guide tube ! end
Figure 5.B.2. Generic TRITON input template for PRISM. (continued)
end materials
read geom
unit 1
com='regular fuel rod'
cylinder 10 .4025
cylinder 20 .411
cylinder 30 .475
cuboid 40 4p0.6295
media 1 1 10
media 4 1 20 -10
media 2 1 30 -20
media 3 1 40 -30
boundary 40 4 4
unit 5
com='guide tube'
cylinder 10 .57175
cylinder 20 .6121
cuboid 40 4p0.6295
media 3 1 10
media 5 1 20 -10
media 3 1 40 -20
boundary 40 4 4
unit 11
com='right half of fuel rod'
cylinder 10 .4025 chord +x=0
cylinder 20 .411 chord +x=0
cylinder 30 .475 chord +x=0
cuboid 40 0.6295 0.0 2p0.6295
media 1 1 10
media 4 1 20 -10
media 2 1 30 -20
media 3 1 40 -30
boundary 40 2 4
unit 12
com='top half of fuel rod'
cylinder 10 .4025 chord +y=0
cylinder 20 .411 chord +y=0
cylinder 30 .475 chord +y=0
cuboid 40 2p0.6295 0.6295 0.0
media 1 1 10
media 4 1 20 -10
media 2 1 30 -20
media 3 1 40 -30
boundary 40 4 2
unit 51
com='right half of guide tube'
cylinder 10 .5715 chord +x=0
cylinder 20 .6121 chord +x=0
cuboid 40 0.6295 0.0 2p0.6295
media 3 1 10
media 5 1 20 -10
media 3 1 40 -20
boundary 40 2 4
unit 52
com='top half of guide tube'
cylinder 10 .5715 chord +y=0
cylinder 20 .6121 chord +y=0
cuboid 40 2p0.6295 0.6295 0.0
media 3 1 10
media 5 1 20 -10
media 3 1 40 -20
boundary 40 4 2
unit 53
com='1/4 instrument tube'
cylinder 10 .5715 chord +x=0 chord +y=0
cylinder 20 .6121 chord +x=0 chord +y=0
cuboid 40 0.6295 0.0 0.6295 0.0
media 3 1 10
media 5 1 20 -10
media 3 1 40 -20
boundary 40 2 2
global unit 10
cuboid 10 10.7015 0.0 10.7015 0.0
array 1 10 place 1 1 0 0
media 3 1 10
boundary 10 34 34
end geom
read array
ara=1 nux=9 nuy=9 typ=cuboidal
fill
53 12 12 52 12 12 52 12 12
11 1 1 1 1 1 1 1 1
11 1 1 1 1 1 1 1 1
51 1 1 5 1 1 5 1 1
11 1 1 1 1 1 1 1 1
11 1 1 1 1 5 1 1 1
51 1 1 5 1 1 1 1 1
11 1 1 1 1 1 1 1 1
11 1 1 1 1 1 1 1 1
end fill
end array
read bounds
all=refl
end bounds
end model
end
=shell
cp ft33f001.cmbined $RTNDIR/namelibrary
end
5.1.9.2. ARPLIB
Warning
ARPLIB is deprecated and replaced by the command line utility OBIWAN (see Sect. 5.2 for details).
ARPLIB is a utility program designed to read a burnup-dependent binary ORIGEN-ARP cross-section library and copy the cross-section data from only the desired burnup positions to create a new ORIGEN-ARP cross-section library.
The input for ARPLIB is described in Table 5.1.18. A new library (OUTLIB) is created by listing the positions from one or more existing libraries to copy to the new library.
An example of the input to ARPLIB is given in Example 5.1.44, showing how to use ARPLIB to reduce the number of cross sections sets on a library by creating a new library with only certain positions retained from the old library.
Parameter |
Description |
Comments |
OUTLIB |
Filename of output library to create |
This library should not already exist |
NLIB |
Number of input libraries to read |
|
For each input library, i up to NLIB |
||
LIBNAME[i] |
Filename of input library to read |
|
NPOS[i] |
Number of positions to read from this i-th library |
>0 |
p1 p2 … |
The list of position indices from this i-th library to put on the output library |
NPOS[i] position indices are read from a single line (all position indices are >0) |
'get an ORIGEN library files for testing
=shell
cp "${DATA}/arplibs/w17_e30.f33" 1_f33
end
'create a new library (ft33f001) with every-other burnup points
=arplib
ft33f001
1
1_f33
8
1 3 5 7 9 11 13 15
end
5.1.9.3. XSECLIST
Warning
ARPLIB is deprecated and replaced by the command line utility OBIWAN (see Sect. 5.2 for details).
The XSECLIST program is intended to provide an interpreted listing of any ORIGEN-ARP cross-section library. This utility program allows users to list the absorption and/or fission cross sections of any or all nuclides in the library as a function of burnup. The absorption cross sections are given for light elements, actinides, and fission products. Some of the light-element isotopes in the library may appear also as fission products; therefore, some isotopes may be listed twice. Fission cross sections may be listed for any or all actinides for which nonzero values of the cross sections exist. ORIGEN-S cross sections are typically normalized to thermal flux, rather than the total flux.
The nuclide ID numbers used in the library listings have the form IZ*10000+IA*10+IS, where
IZ = the atomic number;
IA = the atomic weight;
IS = 0, for ground state;
IS = 1, for metastable state.
The XSECLIST input is described in Table 5.1.19. The input is free format. The user specifies the library filename, the total number of burnup positions in the library, and the burnup values (GWd/MTU) corresponding to each burnup position. The user then indicates whether the cross-section data listings are for absorption, fission, or both; and whether the listings are for all nuclides or only certain specified ones.
An example input file for XSECLIST is shown in Example 5.1.45. This example contains two cases: The first case lists both absorption and fission cross sections for 240Pu in the ORIGEN-ARP 5 wt % enriched PWR 14 \(\times\) 14 basic cross-section library. The output listing for this case is displayed in Example 5.1.46. These are microscopic cross sections listed in units of barns. The second case lists the fission cross sections for all nuclides in the ORIGEN-ARP 1.5 wt % enriched PWR 14 \(\times\) 14 basic cross-section library. The output from this case is not presented here because of its size.
Line No. |
Parameter |
Description |
Comments |
1 |
FILENAME |
Library filename |
30-character maximum |
2 |
NL |
Number of burnup positions in library |
|
32 |
BURN |
Burnup (GWd/MTU) of each burnup position in library |
NL entries required |
4 |
CHARD |
Cross-section data to be printed |
a = absorption f = fission b = both |
5 |
CHARL |
List entire library (all nuclides) |
y = yes n = no |
NOTE: The following optional data are entered only if CHARL = n. |
|||
6 |
MT |
Number of nuclides for which cross-section listings are desired |
|
72 |
MTRD |
Nuclide IDs 3 |
MT entries required |
- 2(1,2)
May be continued on subsequent lines as needed.
- 3
Nuclide ID = Atomic No. * 10000 + Atomic wt * 10 + IS, where IS = 0 for ground state and 1 for metastable state.
=xseclist
ce14_e50.arplib
10
0.0 1.5 4.5 7.5 10.5 13.5 16.5 31.5
46.5 58.5
b
n
1
942400
end
=xseclist
ce14_e15.arplib
10
0.0 1.5 4.5 7.5 10.5 13.5 16.5 31.5
46.5 58.5
f
y
end
\*****\* absorption cross sections \*****\*
----------- light elements -----------
------- end of light elements --------
------------- actinides --------------
material= 942400 (pu240 )
burnup xsec
0.00000E+00 1.65356E+03
1.50000E+00 1.69928E+03
4.50000E+00 1.60593E+03
7.50000E+00 1.47163E+03
1.05000E+01 1.34200E+03
1.35000E+01 1.22895E+03
1.65000E+01 1.13326E+03
3.15000E+01 8.27437E+02
4.65000E+01 6.82870E+02
5.85000E+01 6.15974E+02
--------- end of actinides -----------
--------- fission products ----------
------ end of fission products -------
\****\* end of absorption cross sections \***\*
\*****\* fission cross sections \*****\*
material= 942400 (pu240 )
burnup xsec
0.00000E+00 4.51353E+00
1.50000E+00 4.71392E+00
4.50000E+00 4.82682E+00
7.50000E+00 4.89713E+00
1.05000E+01 4.93990E+00
1.35000E+01 4.96174E+00
1.65000E+01 4.96700E+00
3.15000E+01 4.82935E+00
4.65000E+01 4.56642E+00
5.85000E+01 4.34749E+00
\****\* end of fission cross sections \****\*