PRISM ===== .. warning:: PRISM is deprecated and replaced by Sampler (see :numref:`sec-sampler` 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 :numref:`ex-origen-prism` and :numref:`ex-origen-prism-out`. In this example a TRITON input file for a Westinghouse 17 :math:`\times` 17 fuel assembly (:numref:`ex-origen-prism-out`) is processed by PRISM using the input file for PRISM listed in :numref:`ex-origen-prism`. The case generates 6 specific input files from the template file. .. tabularcolumns:: |p{1.5cm}|p{2cm}|p{5cm}|p{5cm}| .. table:: PRISM input description :name: tab-origen-prism :widths: 10 20 35 35 :class: longtable +----------------+----------------+-----------------+----------------+ | **Line No.** | **Parameter** | **Description** | **Comments** | +----------------+----------------+-----------------+----------------+ | 1 | TEMPLATE | Template file | 80 characters | | | | name | maximum | +----------------+----------------+-----------------+----------------+ | 2 | OUT_TEMPLATE | Pattern for | 80 characters | | | | output file | maximum | | | | names | | | | | | 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 | 80 characters | | | | parameter name | maximum | | | | as it appears | | | | | in template | | | | | file | | +----------------+----------------+-----------------+----------------+ | 5 [#f1]_ | PARAMETERS | Specific | NUMFILES | | | | values of | entries | | | | generic | required. | | | | parameter for | Length of | | | | each output | value must be | | | | file | same as length | | | | | of PARAM_NAME | +----------------+----------------+-----------------+----------------+ .. [#f1] May be continued on subsequent lines as needed. .. code-block:: scale :name: ex-origen-prism :caption: PRISM input example to generate TRITON input files. =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 .. code-block:: scale :name: ex-origen-prism-out :caption: Generic TRITON input template for PRISM. =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 ARPLIB ====== .. warning:: ARPLIB is deprecated and replaced by the command line utility OBIWAN (see :numref:`sec-obiwan` 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 :numref:`tab-origen-arplib`. 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 :numref:`ex-origen-arplib`, 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. .. tabularcolumns:: |p{1.5cm}|p{4cm}|p{4cm}| .. table:: ARPLIB input description :name: tab-origen-arplib :widths: 15 40 35 :class: longtable +---------------+-------------------------+-------------------------+ | **Parameter** | **Description** | **Comments** | +---------------+-------------------------+-------------------------+ | OUTLIB | Filename of output | This library should not | | | library to create | 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 | >0 | | | read from this i-th | | | | library | | +---------------+-------------------------+-------------------------+ | p1 p2 … | The list of position | NPOS[i] position | | | indices from this i-th | indices are read from a | | | library to put on the | single line (all | | | output library | position indices are | | | | >0) | +---------------+-------------------------+-------------------------+ .. code-block:: scale :caption: ARPLIB example input to reduce size of ORIGEN cross-section libraries. :name: ex-origen-arplib '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 XSECLIST ======== .. warning:: ARPLIB is deprecated and replaced by the command line utility OBIWAN (see :numref:`sec-obiwan` 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 :numref:`tab-origen-xseclist`. 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 :numref:`ex-origen-xseclist`. This example contains two cases: The first case lists both absorption and fission cross sections for :sup:`240`\ Pu in the ORIGEN-ARP 5 wt % enriched PWR 14 :math:`\times` 14 basic cross-section library. The output listing for this case is displayed in :numref:`ex-origen-xseclist-pu240`. 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 :math:`\times` 14 basic cross-section library. The output from this case is not presented here because of its size. .. tabularcolumns:: |p{1.5cm}|p{2cm}|p{5cm}|p{5cm}| .. table:: XSECLIST input description :name: tab-origen-xseclist :widths: 10 20 35 35 :class: longtable +----------------+----------------+-----------------+------------------+ | **Line No.** | **Parameter** | **Description** | **Comments** | +----------------+----------------+-----------------+------------------+ | 1 | FILENAME | Library | 30-character | | | | filename | maximum | +----------------+----------------+-----------------+------------------+ | 2 | NL | Number of | | | | | burnup | | | | | positions in | | | | | library | | +----------------+----------------+-----------------+------------------+ | 3\ [#f2]_ | BURN | Burnup | NL entries | | | | (GWd/MTU) of | required | | | | each burnup | | | | | position in | | | | | library | | +----------------+----------------+-----------------+------------------+ | 4 | CHARD | Cross-section | a = absorption | | | | data to be | | | | | printed | f = fission | | | | | | | | | | b = both | +----------------+----------------+-----------------+------------------+ | 5 | CHARL | List entire | y = yes | | | | library (all | | | | | nuclides) | 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 | | +----------------+----------------+-----------------+------------------+ | 7\ [#f2]_ | MTRD | Nuclide | MT entries | | | | IDs [#f3]_ | required | +----------------+----------------+-----------------+------------------+ .. [#f2] May be continued on subsequent lines as needed. .. [#f3] Nuclide ID = Atomic No. \* 10000 + Atomic wt \* 10 + IS, where IS = 0 for ground state and 1 for metastable state. .. code-block:: scale :caption: XSECTLIB input example :name: ex-origen-xseclist =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 .. code-block:: none :caption: XSECLIST listing of :sup:`240`\ Pu data. :name: ex-origen-xseclist-pu240 \*****\* 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 \****\*