PL-ORI - is a code, developed by O. Gritzay, for presentation of the ENDF formatted cross sections (MF=3), obtained after processing by any from codes LINEAR, RECENT, SIGMA1, GROUPIE or MIXER in a table format. This code can be used as a very simple and useful tools to prepare input file for the graphical package MicrocalTMOriginTM (see ).

        A task input file may have arbitrary name, the ENDF formatted input file is not changed, the resulting files are written in the sub-directory FOR_ORI, amount of them is depend on selected option.

The names of these resulting files are created by this code itself the following way:
         The first three letters correspond to an isotope atomic number A, e.g., for H A=001;
         The next two letters correspond to an abbreviated name of material or an abbreviated name of material plus a lower hyphen "_" (if this abbreviated name of material consists of one letter). For example, Co or H_;
         The next three letters correspond to MT number (type of reaction).

Extension of resulting files always is *.dat.

The requirements to the task input file are presented in the file PL-ORI.DOC.



Column (format)

Explanation of parameters


1-12 (12)

ENDF/B input data filename


1-4 (I4)

MAT number of given material
If MAT = 0, the code execution is terminated.


1-2 (I2)

MF number file, from which data are selected

3 (1)


4-6 (3)

MT number (type of reaction)

From one input ENDF file it may chose data for several materials MAT, files MF or type of reactions MAT and obtain each time new separate output file with data in table format. To do it, repeat needed times the lines 2 and 3 in task input file. The order of data choose is arbitrary.

Resulting output files will be created in subdirectory FOR_ORI (before first running of this code it will be created).

Name of resulting output files will be created by code itself and its name carries information about atomic number of material, name of material and type of reaction.

The program execution is terminated by the second line containing 0 (zero).

        To facilitate the work with PL-ORI we present an example of the task input file named INP

   Let RESULT.3  is ENDF formatted file after processing by SIGMA1 
and it contains data for 1-H-1 (MT=125), 92-U-235 (MT=9228) and several other materials. 
Let we wish to create separate files with table data (#, energy, cross section) for 
total neutron cross section (MT=1) of 1-H-1 (MAT=125), and for
total neutron cross section (MT=1) and elastic cross section (MT=2) of 92-U-235 (MAT=9228).

INP file RESULT.3 9228 3 1 125 3,1 9228 3 2 0 Running of this code: PL_ORI < INP

	If you run this code as PL_ORI (without < INP)
you have to type all needed parameters on keyboard finishing each line by ENTER. 

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