DLC-0142 ZZ-KERMAL.

1. NAME OR DESIGNATION OF PROGRAM:  KERMAL.

3. DESCRIPTION OF PROGRAM OR FUNCTION



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Calculated NEUTRON KERMA Factors

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  FORMAT: TART Monte Carlo neutron transport code



  NUMBER OF GROUPS: 175 neutron energy groups



NUCLIDES: tissue, bone, muscle, standard man, plastic,nylon-6.6/6,  Lucite, liquid muscle equivalent, water, acetylene, dry air, water-saturated air, carbon dioxide, Ethylene, Te gas with methane.


  ORIGIN: LLNL Evaluated Nuclear Data Library (ENDL)



  WEIGHTING SPECTRUM: --





Calculated PHOTON KERMA Factors

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  FORMAT: TART Monte Carlo neutron transport code



  NUMBER OF GROUPS: 191 energy groups



NUCLIDES: tissue, bone, muscle, standard man, plastic,nylon-6.6/6,  Lucite, liquid muscle equivalent, water, acetylene, dry air, water-saturated air, carbon dioxide, Ethylene, Te gas with methane.


  ORIGIN: LLNL Evaluated Gamma-Ray Data Library (ENDL)



  WEIGHTING SPECTRUM: --



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    These libraries contain neutron and gamma ray KERMA factors.

KENDL, the neutron KERMA factors have been calculated from the LLNL Evaluated Nuclear Data Library (ENDL) data file. The results are for the 175 neutron energy groups used by the TART Monte Carlo neutron transport code for isotopes and elemental mixtures. They are tabulated for 15 composite materials and for the isotopes or elements in the ENDL file from Z=1 to Z=29. The incident neutron energies range from 1.882 x 1.0E-5 to 20 MeV for the composite materials and from 1.307 x 1.0E-9 to 20 MeV for the isotopes and elements.

KEGDL, the gamma-ray KERMA factors calculated from the LLNL Evaluated Gamma-Ray Data Library (EGDL) file, are tabulated for the  elements from Z=1 to Z=30 and for 15 composite materials. The KERMA  factors are presented for 191 energy groups over the incident photon energy range from 100 eV to 100 MeV.

The following composite materials are tabulated: tissue, bone, muscle, standard man, plastic, nylon-6.6/6, Lucite, liquid muscle equivalent, water, acetylene, dry air, water-saturated air, carbon dioxide, gas Te with methane.

4. METHOD OF SOLUTION:

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

NEA/DB ran the test case of the data retrieval program  on the data library in 0.35 seconds on a VAXStation 3100 M38.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS

The tabulations are used by the Monte Carlo neutron transport code TART.

10. REFERENCES:

- R.J. Howerton:
  Calculated Neutron KERMA Factors Based on the LLNL ENDL Data File
  UCRL-50400, Vol. 27 (January 1986).
- R.J. Howerton:
  Calculated Photon KERMA Factors Based on the LLNL EGDL Data File
  UCRL-50400, Vol. 29 (October 1986).

11. MACHINE REQUIREMENTS:

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

NEA-DB executed the data retrieval program on a VAXSTation 3100 M38 running VAX/VMS Version 6.1. The source was compiled with the VAX Fortran compiler Version 6.2-108.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHORS

      Lawrence Livermore National Laboratory
      LIVERMORE, California, U. S. A.

File name	File description	Records
DLC0142_01.001	Information file	69
DLC0142_01.002	Sample input	3
DLC0142_01.003	Neutron kerma factors	6200
DLC0142_01.004	Gamma kerma factors	1992
DLC0142_01.005	FORTRAN 77 source retrieval program	49
DLC0142_01.006	Sample output	356
DLC0142_01.007	JCL file to compile, link and execute on IBM	11
DLC0142_01.008	JCL file to compile, link & execute VAX/VMS	6