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Changes for generating input to XGEN.
- Use xgen for the material number to get a xgen input file - Examples using dry air - New Windows executable - Notes for this version of the code
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Dry Air | ||
3 | ||
Standard Density: 1.205e-3 g/cc @ 20 deg C, 1 atm | ||
See "Introduction to Radiological Physics | ||
and Radiation Dosimetry" by Attix p.531-532 | ||
1.205e-3 | ||
weight | ||
4 | ||
nat 6 0.000124 | ||
nat 7 0.755268 | ||
nat 8 0.231781 | ||
nat 18 0.012827 | ||
100 |
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C | ||
C Dry Air | ||
C | ||
C Standard Density: 1.205e-3 g/cc @ 20 deg C, 1 atm | ||
C See "Introduction to Radiological Physics | ||
C and Radiation Dosimetry" by Attix p.531-532 | ||
C | ||
C Summary of MatMCNP (Version 4.1) Calculations: | ||
C | ||
C Isotope Number Fraction Weight Fraction Atoms/b-cm | ||
C C-12 0.000149 0.000123 0.0000000 | ||
C C-13 0.000002 0.000001 0.0000000 | ||
C N-14 0.781575 0.752324 0.0000390 | ||
C N-15 0.002855 0.002944 0.0000001 | ||
C O-16 0.210236 0.231153 0.0000105 | ||
C O-17 0.000080 0.000094 0.0000000 | ||
C O-18 0.000432 0.000535 0.0000000 | ||
C Ar-36 0.000016 0.000039 0.0000000 | ||
C Ar-38 0.000003 0.000008 0.0000000 | ||
C Ar-40 0.004653 0.012781 0.0000002 | ||
C | ||
C The total compound atom density (atom/b-cm): 0.0000499 | ||
C | ||
C | ||
C This material contains an isotope that is often modified by | ||
C an S(alpha,beta). Check MCNP Manual Appendix G to see if an | ||
C S(alpha,beta) card (i.e., an MTn card) is required. | ||
C | ||
M100 06012.00c 0.000149 | ||
06013.00c 0.000002 | ||
07014.00c 0.781575 | ||
07015.00c 0.002855 | ||
08016.00c 0.210236 | ||
08017.00c 0.000080 | ||
08018.00c 0.000432 | ||
18036.00c 0.000016 | ||
18038.00c 0.000003 | ||
18040.00c 0.004653 | ||
C | ||
C To convert a particle flux to rad[Material] | ||
C use FM 6.6316863E-10 100 -4 1 for neutrons | ||
C or FM 6.6316863E-10 100 -5 -6 for photons. | ||
C |
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Dry Air | ||
3 | ||
Standard Density: 1.205e-3 g/cc @ 20 deg C, 1 atm | ||
See "Introduction to Radiological Physics | ||
and Radiation Dosimetry" by Attix p.531-532 | ||
1.205e-3 | ||
weight | ||
4 | ||
nat 6 0.000124 | ||
nat 7 0.755268 | ||
nat 8 0.231781 | ||
nat 18 0.012827 | ||
xgen |
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C | ||
C Dry Air | ||
C | ||
C Standard Density: 1.205e-3 g/cc @ 20 deg C, 1 atm | ||
C See "Introduction to Radiological Physics | ||
C and Radiation Dosimetry" by Attix p.531-532 | ||
C | ||
C Summary of MatMCNP (Version 4.1) Calculations: | ||
C | ||
C Isotope Number Fraction Weight Fraction Atoms/b-cm | ||
C C-12 0.000149 0.000123 0.0000000 | ||
C C-13 0.000002 0.000001 0.0000000 | ||
C N-14 0.781575 0.752324 0.0000390 | ||
C N-15 0.002855 0.002944 0.0000001 | ||
C O-16 0.210236 0.231153 0.0000105 | ||
C O-17 0.000080 0.000094 0.0000000 | ||
C O-18 0.000432 0.000535 0.0000000 | ||
C Ar-36 0.000016 0.000039 0.0000000 | ||
C Ar-38 0.000003 0.000008 0.0000000 | ||
C Ar-40 0.004653 0.012781 0.0000002 | ||
C | ||
C The total compound atom density (atom/b-cm): 0.0000499 | ||
C | ||
C | ||
C This material contains an isotope that is often modified by | ||
C an S(alpha,beta). Check MCNP Manual Appendix G to see if an | ||
C S(alpha,beta) card (i.e., an MTn card) is required. | ||
C | ||
Mxgen 06012.00c 0.000149 | ||
06013.00c 0.000002 | ||
07014.00c 0.781575 | ||
07015.00c 0.002855 | ||
08016.00c 0.210236 | ||
08017.00c 0.000080 | ||
08018.00c 0.000432 | ||
18036.00c 0.000016 | ||
18038.00c 0.000003 | ||
18040.00c 0.004653 | ||
C | ||
C To convert a particle flux to rad[Material] | ||
C use FM 6.6316863E-10 xgen -4 1 for neutrons | ||
C or FM 6.6316863E-10 xgen -5 -6 for photons. | ||
C |
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Notes on changes for MatMCNP Version XGEN | ||
- February 2021 | ||
------------------------------- | ||
|
||
This modification allows the user to create material files for use with the xgen program. XGEN | ||
is a utility code for producing continuous energy electron/photon cross sections for use with the | ||
Integrated Tiger Series (ITS) code system. This modification to MatMCNP does not change any of the | ||
calculations previously discussed and verified. It is simply a new format to output the results. | ||
|
||
To invoke the XGEN input generation, simply replace the material number intended for the MCNP | ||
material number with "xgen". The xgen input uses a default energy of 1.0 MeV which must be changed if | ||
your ITS problem has a different maximum energy. The density output in the xgen input file will need | ||
verification if you are using less density (< 1.0e-5 g/cc) materials. | ||
|
||
With these changes, MatMCNP expects no arguments, 2 arguments, or 3 arguments. | ||
(1) No arguments on the command line: | ||
- Input file: matmcnp.inp | ||
- Output file: matmcnp.out | ||
- XGEN input: matxgen.inp | ||
|
||
(2) Two arguments on the command line: | ||
- Input file: First argument | ||
- Output file: Second argument | ||
- XGEN input: matxgen.inp | ||
|
||
(3) Three arguments on the command line: | ||
- Input file: First argument | ||
- Output file: Second argument | ||
- XGEN input: Third argument | ||
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||
An example using Dry Air has been added. | ||
|
||
New Files: | ||
(1) VersionXGEN_Notes.txt - This file | ||
(2) DryAir_NoXGEN.inp - An input file using original MatMCNP input format | ||
(3) DryAir_NoXGEN.out - Output file from (2) | ||
(4) DryAir_XGEN.inp - A MatMCNP input file that will generate an xgen input | ||
(5) DryAir_XGEN.out - Output file from (4) | ||
(6) XGEN_DryAir.inp - A file that can be used by xgen to generate cross sections for ITS | ||
(7) bin/MatMCNP_vXGEN.exe - A Windows executable built with gfortran using the makefile in /source |
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TITLE | ||
... Dry Air | ||
energy 1.00 | ||
* | ||
* Standard Density: 1.205e-3 g/cc @ 20 deg C, 1 atm | ||
* See "Introduction to Radiological Physics | ||
* and Radiation Dosimetry" by Attix p.531-532 | ||
* | ||
* Summary of MatMCNP (Version 4.1) Calculations: | ||
* | ||
* Isotope Number Fraction Weight Fraction Atoms/b-cm | ||
* C-12 0.000149 0.000123 0.0000000 | ||
* C-13 0.000002 0.000001 0.0000000 | ||
* N-14 0.781575 0.752324 0.0000390 | ||
* N-15 0.002855 0.002944 0.0000001 | ||
* O-16 0.210236 0.231153 0.0000105 | ||
* O-17 0.000080 0.000094 0.0000000 | ||
* O-18 0.000432 0.000535 0.0000000 | ||
* Ar-36 0.000016 0.000039 0.0000000 | ||
* Ar-38 0.000003 0.000008 0.0000000 | ||
* Ar-40 0.004653 0.012781 0.0000002 | ||
* | ||
* The total compound atom density (atom/b-cm): 0.0000499 | ||
* | ||
* | ||
* This material contains an isotope that is often modified by | ||
* an S(alpha,beta). Check MCNP Manual Appendix G to see if an | ||
* S(alpha,beta) card (i.e., an MTn card) is required. | ||
* | ||
MATERIAL | ||
C 0.0001240 | ||
N 0.7552680 | ||
O 0.2317810 | ||
Ar 0.0128270 | ||
DENSITY 0.0012050 |
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