DLC-0010 ZZ-DLC-10B/AVKER.

ZZ DLC-10B AVKER, Neutron Kerma Response Function Data Library

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: ZZ-DLC-10B/AVKER. Neutron kerma response function data and retrieval program.

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2. COMPUTERS

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Program name	Package id	Status	Status date
ZZ-DLC-10B	DLC-0010/01	Tested	01-APR-1973

Machines used:

Package ID	Orig. computer	Test computer
DLC-0010/01	Many Computers	Many Computers

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3. NATURE OF PHYSICAL PROBLEM SOLVED

  FORMAT: --

NUMBER OF GROUPS: Kerma factors at 816 energy points within the energy range 0.023 eV to 19.2 MeV or as kerma factors for a specified group structure.

NUCLIDES: H, Li-6, Li-7, Be, C, N, O, F, Na, Mg, Al, Si, P, S, Cl,  K, Ca, Fe, and Nb.

  ORIGIN: O5R and ENDF/B libraries except for P and F.

  WEIGHTING SPECTRUM: Flat or 1/E.

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The original library was compiled for use in computing energy release in tissue and heating in various materials. The elements compiled for the first library are H, 6-Li, 7-Li, Be, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, K, Ca, Fe, and Nb.
The cross sections used were based on the O5R and ENDF/B libraries except for P, which the authors of ref. 1 compiled, and F  which came from GAM-2.

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4. METHOD OF SOLUTION

The quantity kerma (kinetic energy release in material) is evaluated by an integration over energy of the product of the kerma factor and flux density at any spatial position.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

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6. TYPICAL RUNNING TIME: The sample problem was run on IBM 360/75 in 1 minute.

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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM

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8. RELATED AND AUXILIARY PROGRAMS

The retrieval program AVKER will evaluate fluence-to-kerma factors for any desired composition that can be made from elements in the library. These data can be obtained either as kerma factors at 816 energy points within the energy range 0.023 eV to 19.2 MeV or as kerma factors for a specified group structure averaged with flat or 1/E weighting.

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9. STATUS

Package ID	Status date	Status
DLC-0010/01	01-APR-1973	Tested at NEADB

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10. REFERENCES

- M. Solomito, J.J. Ritts, and H.C. Claiborne:
'AVKER, A Program for Determining Neutron Kerma Factors for Use in Energy Deposition Calculations'
ORNL-TM-2558 (1969).

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11. MACHINE REQUIREMENTS

Standard I/O, standard punch facility, and 1 tape are required.

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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED: IBM OS/360 with FORTRAN-H compiler.

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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The present library is dated Jan. 1970 and contains also data for copper.

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15. NAME AND ESTABLISHMENT OF AUTHOR

     Oak Ridge National Laboratory
     Neutron Physics and Reactor Divisions
     P.O. Box X
     Oak Ridge, Tennessee 37830, U.S.A.
The authors of AVKER see reference under 10.

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16. MATERIAL AVAILABLE

DLC-0010/01

File name	File description	Records
DLC0010_01.001	KERMA LIBRARY NO.2	5461
DLC0010_01.002	AVKER SOURCE PROGRAM	128
DLC0010_01.003	AVKER SAMPLE PROBLEM DATA	18
DLC0010_01.004	AVKER SAMPLE PROBLEM PUNCHED OUTPUT	816
DLC0010_01.005	AVKER SAMPLE PROBLEM OUTPUT	330

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17. CATEGORIES

G. Radiological Safety, Hazard and Accident Analysis
Z. Data.

Keywords: ENDF/B, cross sections, data, kerma factors, kinetics, neutrons.