last modified: 09-JUL-1998 | catalog | categories | new | search |

PSR-0306 KAOS-V

KAOS-V, Neutron Fluence to Kerma Factor Evaluation from ENDF/B-5 and JENDL-2

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1. NAME OR DESIGNATION OF PROGRAM:  KAOS-V (An Evaluation Tool For
Neutron Kerma Factors And Other Nuclear Responses).
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2. COMPUTERS
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Program name Package id Status Status date
KAOS-V PSR-0306/01 Tested 09-JUL-1998

Machines used:

Package ID Orig. computer Test computer
PSR-0306/01 CRAY family PC Pentium 200,RISC 6000,ALPHA/AXP
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3. DESCRIPTION OF PROGRAM OR FUNCTION

KAOS-V evaluates accurately the neutron fluence-to-Kerma factors from microscopic nuclear data.
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4. METHOD OF SOLUTION

Two basic methods for computing kerma factors,  namely kinematics and energy balance, are implemented in KAOS-V. KAOS-V uses data from the evaluated nuclear data files ENDF/B-V. Auxiliary nuclear data bases, such as the Japanese evaluated nuclear data library JENDL-2 can be used as a source of isotopic cross sections. These are needed to estimate average quantities such as effective Q-values for the natural element. For resonance treatment, the code has the ability to access NJOY and NPTXS interface files in formatted or binary forms.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None noted.
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6. TYPICAL RUNNING TIME:  The sample problem took about 1.5 minutes on  the Cray.
PSR-0306/01
NEA Data Bank implemented the program on the following computers: (1) PC with Intel Pentium 200MHz processor; (2) IBM RISC/6000 Workstation; (3) DEC ALPHA Workstation. The execution times of the test case included in the package were (in seconds) 14.45 for (1); 38.51 for (2); 73.89 for (3).
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7. UNUSUAL FEATURES OF THE PROGRAM:
PSR-0306/01
Graphics output is in EPS format.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
PSR-0306/01 09-JUL-1998 Tested at NEADB
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10. REFERENCES:
PSR-0306/01, included references:
- Y. Farawila, Y. Gohar, and C. Maynard:
  KAOS-V Code - An Evaluation Tool for Neutron Kerma Factors and
  Other Nuclear Responses
  ANL/FPP/TM-240 (September 1989).
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11. MACHINE REQUIREMENTS:  The code runs on the Cray computers.
PSR-0306/01
NEA Data Bank implemented the program on the following computers: (1) PC with Intel Pentium 200MHz processor; (2) IBM RISC/6000 Workstation; (3) DEC ALPHA Workstation.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0306/01 FORTRAN-77, FORTRAN-90
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The code was written in FORTRAN 77 under the CTSS operating system. The CFT compiler is used. The plotting routines require the DISSPLA graphics system.
PSR-0306/01
NEA Data Bank implemented the program on the following computers: (1) PC with Intel Pentium 200MHz processor running under MS-DOS (Windows95) with the Lahey compilers f77 5.2 and f90 3.40a; (2) IBM RISC/6000 Workstation running AIX 3.2 and  the compiler xlf; (3) DEC ALPHA Workstation running OSF/1 and the compiler f77.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
PSR-0306/01
The VIEWR module of NJOY-94 has been included to replace DISSPLA.
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15. NAME AND ESTABLISHMENT OF AUTHORS: , Argonne National Laboratory, Argonne, Illinois
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16. MATERIAL AVAILABLE
PSR-0306/01
source program   mag tapeKAOSV Source File (FTN77)                  SRCTP
test-case data   mag tapeINPUT S.I. for Natural Titanium            DATTP
test-case data   mag tapeTAPE1 Ener. Depend. Q-values Ti(n,2n) Reac.DATTP
test-case data   mag tapeTAPE2 Ener. Depend. Q-values Ti(n,p) Reac. DATTP
test-case data   mag tapeTAPE3 Ener. Depend. Q-values Ti(n,alpha)   DATTP
test-case data   mag tapeGROUP VITAMIN-E Group Structure            DATTP
test-case data   mag tapeNATURAL Natural Titanium File              DATTP
test-case data   mag tapeRESPONSE Standard Response File            DATTP
test-case output mag tapeDIAGNOSE Output Diagnostics                OUTTP
test-case output mag tapeOUTPUT Sample Output for Titanium          OUTTP
report                   ANL/FPP/TM-240 (September 1989)            REPPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: kerma factors, neutron.