Preparation of the Pseudo Fission Product Cross Sections for the WIMS-D Library

D. L. Aldama, A. Trkov

(Rev.0: 26 April 1999)
(Rev.1: 21 October 1999)
(Rev.2: 11 January 2000)

1. Background

The steps for updating the decay data, fission product yields and pseudo fission product cross sections in the WIMS-D library should be performed in the following sequence:

Prepare the fission product yields data (*.NJB files) and the pseudo fission product processing inputs (NJOY and WILLIE inputs) according to the procedure described below.
Run NJOY to produce cross sections for all fission products that are not explicitly represented.
Run WILLIE to assemble the pseudo fission product cross sections.
Run NJINJB to insert the fission product yield data into the master NJOY input file.

Instructions for actually updating the WIMS-D Library are given separately.

2. Implement auxiliary programs and procedures.

Prepare the following merged files of the corresponding evaluated nuclear data libraries and put them on your WLUP\INPUTS subdirectory. Not that fixed filenames are assumed, according to the table below.

Library	Cross section data file name	Decay data filename	Fission yield data file name
ENDF/B-VI	`endfb6nt.dat`	`endfb6dy.dat`	`endfb6fp.dat`
JEF 2.2	`jef22nt.dat`	`jef22dy.dat`	`jef22fp.dat`
JENDL	`jendlnt.dat`	`jendldy.dat`	`jendlfp.dat`
CENDL	`jendlnt.dat`	`jendldy.dat`	`jendlfp.dat`
BROND	`brondnt.dat`	`bronddy.dat`	`brondfp.dat`
FOND	`fondnt.dat`	`fonddy.dat`	`bondfp.dat`
JEFF3	`jeff3nt.dat`	`jeff3dy.dat`	`jeff3fp.dat`
generic	`endlnt.dat`	`endldy.dat`	`endlfp.dat`

Download the following files to the WLUP\PROGRAMS\ subdirectory:

AVRFPY.FOR
GETDATA.FOR
NJBFP.FOR
PSEUDO.FOR
NJINJB.FOR
NJISPL.FOR
WILLIE.FOR
PSEUDO1.BAT
PSEUDOFP.BAT

Download the following files to the WLUP\INPUTS\ subdirectory:

FpLstExp.dat: List of explicitly represented fission product.
FpLstAll.dat: List of all considered fission product.
Eaf97.int: INTER output file from the EAF-97 European Activation File eventually needed by AVRFPY.
Actlst.dat: List of actinides.

Prepare the executable programs of the downloaded FORTRAN codes on your WLUP\PROGRAMS\ subdirectory.
Copy the procedure PSEUDOFP.BAT from your WLUP\PROGRAMS\ to your WLUP\WORK\ subdirectory.

3. Create the NJOY and WILLIE inputs to generate the pseudo fission product cross sections.

Set your WLUP\WORK\ subdirectory as the default directory.
Adjust the definitions in the SETWLUP.BAT file in the \WLUP\PROGRAMS directory to your local environment.
Define the WLUP environment variables with the \WLUP\PROGRAMS\SETWLUP command.
Type the following command according to corresponding evaluated nuclear data library:

Library	Command
ENDF/B-VI	pseudofp endfb6 eaf97
JEF 2.2	pseudofp jef22 eaf97
JENDL	pseudofp jendl eaf97
CENDL	pseudofp cendl eaf97
BROND	pseudofp brond eaf97
FOND	pseudofp fond eaf97
JEFF3	pseudofp jeff3 eaf97
generic	pseudofp endl eaf97

The second parameter is optional or you can use your own INTER output file.

The procedure pseudofp performs the following tasks:

For each actinide explicitly represented in the WIMS library:

Generate using AVRFPY the intermediate *.FPY file with the most relevant decay and fission product yield data.
Prepare the corresponding fission product yields for those fission products included in the list file FpLstExp.dat using AVRFPY.
Prepare the corresponding fission product yields for those fission products included in the list file FpLstAll.dat using AVRFPY.
Check consistency of the previous outputs, calculate the pseudo-fission product yield and prepare the fission yield block needed for WIMSR inputs using NJBFP.

90232GI.NJB

91233GI.NJB

92233GI.NJB

92234GI.NJB

92235GI.NJB

92236GI.NJB

92237GI.NJB

92238GI.NJB

93237GI.NJB

93239GI.NJB

94238GI.NJB

94239GI.NJB

94240GI.NJB

94241GI.NJB

94242GI.NJB

95241GI.NJB

95242MI.NJB

95243GI.NJB

96242GI.NJB

96243GI.NJB

96244GI.NJB

The file names begin with the ZA number of the corresponding actinide. (U235ŕ 92235GI.NJI).

To include these files in the NJOY input option file (endfb6.nji, jef22.nji, etc.) the code NJINJB is also available on the WLUP web site.

From the data prepared for U-235, U-238 and Pu-239 the corresponding files to generate the pseudo fission product 4902 are created using the PSEUDO code. They are named according to the evaluated nuclear data library and archived in the appropriate directory as evident from the table below. A copy of the newly generated files is placed on the default directory for later use. The source evaluated nuclear data file is also copied to "TAPE20." on the default directory.

Library	NJOY input file (*.nji) on WLUP\INPUTS	WILLIE input file (*.wli) on WLUP\INPUTS	DOS/WINDOWS BATCH file on WLUP\PROGRAMS
ENDF/B-VI	endfb6fp.nji	endfb6fp.wli	endfb6fp.bat
JEF 2.2	jef22fp.nji	jef22fp.wli	jef22fp.bat
JENDL	jendlfp.nji	jendlfp.wli	jendlfp.bat
CENDL	jendlfp.nji	jendlfp.wli	jendlfp.bat
BROND	brondfp.nji	brondfp.wli	brondfp.bat
FOND	fondfp.nji	fondfp.wli	bondfp.bat
JEFF3	jeff3fp.nji	jeff3fp.wli	jeff3fp.bat
generic	endlfp.nji	endlfp.wli	endlfp.bat

Brief description of the output files:

The following files are also created if the corresponding data are available:

"zae".FPY : AVRFPY fission product yield and decay data file.

"zae"x.NJB: AVRFPY burnup data file for nuclides listed in FpLstExp.dat

"zae"x.OUT: AVRFPY output file for nuclides listed in FpLstExp.dat

"zae"a.NJB: AVRFPY burnup data file for nuclides listed in FpLstAll.dat

"zae"a.OUT: AVRFPY output file for nuclides listed in FpLstAll.dat

"zae"i.NJB: NJBFP fission product yield file for WIMSR input.

where,

"za" is the ZA symbol (U-235 ŕ 92235)

"e" = G for ground state

= M for metastable

If one of the fission products does not have cross section data in the library it is automatically omitted and the code writes a warning message. If one of the actinides does not have fission product data then the *.FPY file is empty and the procedure will write the corresponding message after AVRFPY crashes.

4. Generate the pseudo fission product cross sections

The NJOY nuclear data processing system is used to generate the cross sections for all nuclides that constitute the pseudo fission product. The WILLIE code is used to assemble the pseudo fission product cross sections. The procedure is applicable to the DOS/Windows systems.

Set the WLUP environment using the SETWLUP procedure.
Unless already available from the previous step, copy the batch file, the NJOY and WILLIE inputs generated in the previous step onto the WLUP\WORK\ subdirectory.
Unless already done in the previous step, copy the evaluated nuclear data library to TAPE20.
Type the following command according to the processed library:

Library	Command
ENDF/B-VI	endfb6fp endfb6
JEF 2.2	jef22fp jef22
JENDL	jendlfp jendl
CENDL	cendlfp cendl
BROND	brondfp brond
FOND	fondfp fond
JEFF3	jeff3fp jeff3
generic	endlfp endl

As result of this stage the following files are created:

PFP4902.XSW on your WLUP\WORK\ subdirectory and a backup of this file on your WLUP\INPUTS\ subdirectory, renamed according to the following table:

Library	XSW file
ENDF/B-VI	`endfb6fp.xsw`
JEF 2.2	`jef22fp.xsw`
JENDL	`jendlfp.xsw`
CENDL	`cendlfp.xsw`
BROND	`brondfp.xsw`
FOND	`fondfp.xsw`
JEFF3	`jeff3fp.xsw`
generic	`endlfp.xsw`

5. Update the fission product yields data in the NJOY input file

The updating process should be performed on the subdirectory on which the "zae"i.NJB files were created. Run NJINJB interactively and supply the appropriate filenames (specify the full path):

\wlup\inputs\ActLst.dat    for the material identifier conversion list file,
\wlup\inputs\'name'.nji    for the NJOY source input where 'name' is "endfb6", "jef22", etc., as appropriate.
wlupnji.inp                for the updated NJOY input file.

Save the updated NJOY input file to the \WLUP\INPUTS\ subdirectory, overwriting the original file, if desired.

You may proceed with the calculations to generate cross sections and update the WIMS-D library according to the RUNDOS batch procedure.