DLC-0049 ZZ-AIRFEWG.

ZZ AIRFEWG, Gamma, Neutron Transport Calculation in Air Using FEWG1 Cross-Section

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: ZZ-AIRFEWG.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
ZZ-AIRFEWG	DLC-0049/01	Tested	20-MAY-1985

Machines used:

Package ID	Orig. computer	Test computer
DLC-0049/01	IBM 360 series	IBM 3081

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3. DESCRIPTION OF PROGRAM OR FUNCTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%

  FORMAT: ANISN

  NUMBER OF GROUPS: 37 neutron / 21 gamma-ray

  NUCLIDES: air (79% N and 21% O)

  ORIGIN: DLC-0031/FEWG1 cross sections (ENDF/B-IV).

  WEIGHTING SPECTRUM: 1/E

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
The AIRFEWG library has been generated by an ANISN multigroup calculation of gamma-ray, neutron, and secondary gamma-ray transport in  infinite homogeneous air using DLC-0031/FEWG1 cross sections.

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4. METHOD OF SOLUTION

The results were generated with a P3, ANISN run with a source in a single energy group. Thus, 58 such runs were required. For sources in the 37 neutron groups, both neutron and secondary gamma-ray fluence results were calculated. For gamma-ray sources only gamma-ray fluences were calculated.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME

NEA-DB executed the test case of the retrieval program EDT303 on IBM 3081K in 114 CPU seconds.

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS: ANISN was used to generate the data library.

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9. STATUS

Package ID	Status date	Status
DLC-0049/01	20-MAY-1985	Tested at NEADB

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10. REFERENCES:

DLC-0049/01, included references:

- J.J. Burgio:
  "Gamma, Neutron and Secondary Gamma Transport in Infinite
  Homogeneous Air":
  Volume 1 - Assumptions, Calculations and Results;
  Volume 2 - Edited Results.
  AFWL-TR-75-303  (December 1975)

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11. MACHINE REQUIREMENTS: EDT303 runs on IBM 3081K in 68K of main storage.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
DLC-0049/01	FORTRAN-IV

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

     Developed by:   Air Force Weapons Laboratory
                     Kirtland Air Force Base
                     New Mexico, U. S. A.

     Contributed by: Radiation Safety Information Computational Center
                     Oak Ridge National Laboratory
                     Oak Ridge, Tennessee, U. S. A.

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16. MATERIAL AVAILABLE

DLC-0049/01

File name	File description	Records
DLC0049_01.001	INFORMATION FILE	52
DLC0049_01.002	NEUTRON GROUP 1 (1/E)	1916
DLC0049_01.003	NEUTRON GROUP 2 (1/E)	1882
DLC0049_01.004	NEUTRON GROUP 3 (1/E)	1850
DLC0049_01.005	NEUTRON GROUP 4 (1/E)	1816
DLC0049_01.006	NEUTRON GROUP 5 (1/E)	1784
DLC0049_01.007	NEUTRON GROUP 6 (1/E)	1750
DLC0049_01.008	NEUTRON GROUP 7 (1/E)	1718
DLC0049_01.009	NEUTRON GROUP 8 (1/E)	1684
DLC0049_01.010	NEUTRON GROUP 9 (1/E)	1652
DLC0049_01.011	NEUTRON GROUP 10 (1/E)	1618
DLC0049_01.012	NEUTRON GROUP 11 (1/E)	1586
DLC0049_01.013	NEUTRON GROUP 12 (1/E)	1552
DLC0049_01.014	NEUTRON GROUP 13 (1/E)	1520
DLC0049_01.015	NEUTRON GROUP 14 (1/E)	1486
DLC0049_01.016	NEUTRON GROUP 15 (1/E)	1454
DLC0049_01.017	NEUTRON GROUP 16 (1/E)	1420
DLC0049_01.018	NEUTRON GROUP 17 (1/E)	1388
DLC0049_01.019	NEUTRON GROUP 18 (1/E)	1354
DLC0049_01.020	NEUTRON GROUP 19 (1/E)	1322
DLC0049_01.021	NEUTRON GROUP 20 (1/E)	1288
DLC0049_01.022	NEUTRON GROUP 21 (1/E)	1256
DLC0049_01.023	NEUTRON GROUP 22 (1/E)	1222
DLC0049_01.024	NEUTRON GROUP 23 (1/E)	1190
DLC0049_01.025	NEUTRON GROUP 24 (1/E)	1156
DLC0049_01.026	NEUTRON GROUP 25 (1/E)	1124
DLC0049_01.027	NEUTRON GROUP 26 (1/E)	1090
DLC0049_01.028	NEUTRON GROUP 27 (1/E)	1058
DLC0049_01.029	NEUTRON GROUP 28 (1/E)	1024
DLC0049_01.030	NEUTRON GROUP 29 (1/E)	992
DLC0049_01.031	NEUTRON GROUP 30 (1/E)	958
DLC0049_01.032	NEUTRON GROUP 31 (1/E)	926
DLC0049_01.033	NEUTRON GROUP 32 (1/E)	892
DLC0049_01.034	NEUTRON GROUP 33 (1/E)	860
DLC0049_01.035	NEUTRON GROUP 34 (1/E)	826
DLC0049_01.036	NEUTRON GROUP 35 (1/E)	794
DLC0049_01.037	NEUTRON GROUP 36 (1/E)	760
DLC0049_01.038	NEUTRON GROUP 37 (1/E)	728
DLC0049_01.039	GAMMA GROUP 1 (1/E)	526
DLC0049_01.040	GAMMA GROUP 2 (1/E)	502
DLC0049_01.041	GAMMA GROUP 3 (1/E)	476
DLC0049_01.042	GAMMA GROUP 4 (1/E)	452
DLC0049_01.043	GAMMA GROUP 5 (1/E)	426
DLC0049_01.044	GAMMA GROUP 6 (1/E)	402
DLC0049_01.045	GAMMA GROUP 7 (1/E)	376
DLC0049_01.046	GAMMA GROUP 8 (1/E)	352
DLC0049_01.047	GAMMA GROUP 9 (1/E)	326
DLC0049_01.048	GAMMA GROUP 10 (1/E)	302
DLC0049_01.049	GAMMA GROUP 11 (1/E)	276
DLC0049_01.050	GAMMA GROUP 12 (1/E)	252
DLC0049_01.051	GAMMA GROUP 13 (1/E)	226
DLC0049_01.052	GAMMA GROUP 14 (1/E)	202
DLC0049_01.053	GAMMA GROUP 15 (1/E)	176
DLC0049_01.054	GAMMA GROUP 16 (1/E)	152
DLC0049_01.055	GAMMA GROUP 17 (1/E)	126
DLC0049_01.056	GAMMA GROUP 18 (1/E)	102
DLC0049_01.057	GAMMA GROUP 19 (1/E)	76
DLC0049_01.058	GAMMA GROUP 20 (1/E)	52
DLC0049_01.059	GAMMA GROUP 21 (1/E)	26
DLC0049_01.060	COEFFICIENTS FOR FITTED RESULTS	1711
DLC0049_01.061	NEUTRON GROUP 1 (FISSION)	1916
DLC0049_01.062	NEUTRON GROUP 2 (FISSION)	1882
DLC0049_01.063	NEUTRON GROUP 3 (FISSION)	1850
DLC0049_01.064	NEUTRON GROUP 4 (FISSION)	1816
DLC0049_01.065	NEUTRON GROUP 5 (FISSION)	1784
DLC0049_01.066	NEUTRON GROUP 6 (FISSION)	1750
DLC0049_01.067	NEUTRON GROUP 7 (FISSION)	1718
DLC0049_01.068	NEUTRON GROUP 8 (FISSION)	1684
DLC0049_01.069	NEUTRON GROUP 9 (FISSION)	1652
DLC0049_01.070	NEUTRON GROUP 10 (FISSION)	1618
DLC0049_01.071	NEUTRON GROUP 11 (FISSION)	1586
DLC0049_01.072	NEUTRON GROUP 12 (FISSION)	1552
DLC0049_01.073	NEUTRON GROUP 13 (FISSION)	1520
DLC0049_01.074	NEUTRON GROUP 14 (FISSION)	1486
DLC0049_01.075	NEUTRON GROUP 15 (FISSION)	1454
DLC0049_01.076	NEUTRON GROUP 16 (FISSION)	1420
DLC0049_01.077	NEUTRON GROUP 17 (FISSION)	1388
DLC0049_01.078	NEUTRON GROUP 18 (FISSION)	1354
DLC0049_01.079	NEUTRON GROUP 19 (FISSION)	1322
DLC0049_01.080	NEUTRON GROUP 20 (FISSION)	1288
DLC0049_01.081	NEUTRON GROUP 21 (FISSION)	1256
DLC0049_01.082	NEUTRON GROUP 22 (FISSION)	1222
DLC0049_01.083	NEUTRON GROUP 23 (FISSION)	1190
DLC0049_01.084	NEUTRON GROUP 24 (FISSION)	1156
DLC0049_01.085	NEUTRON GROUP 25 (FISSION)	1124
DLC0049_01.086	NEUTRON GROUP 26 (FISSION)	1090
DLC0049_01.087	NEUTRON GROUP 27 (FISSION)	1058
DLC0049_01.088	NEUTRON GROUP 28 (FISSION)	1024
DLC0049_01.089	NEUTRON GROUP 29 (FISSION)	992
DLC0049_01.090	NEUTRON GROUP 30 (FISSION)	958
DLC0049_01.091	NEUTRON GROUP 31 (FISSION)	926
DLC0049_01.092	NEUTRON GROUP 32 (FISSION)	892
DLC0049_01.093	NEUTRON GROUP 33 (FISSION)	860
DLC0049_01.094	NEUTRON GROUP 34 (FISSION)	826
DLC0049_01.095	NEUTRON GROUP 35 (FISSION)	794
DLC0049_01.096	NEUTRON GROUP 36 (FISSION)	760
DLC0049_01.097	NEUTRON GROUP 37 (FISSION)	728
DLC0049_01.098	GAMMA GROUP 1 (FISSION)	526
DLC0049_01.099	GAMMA GROUP 2 (FISSION)	502
DLC0049_01.100	GAMMA GROUP 3 (FISSION)	476
DLC0049_01.101	GAMMA GROUP 4 (FISSION)	452
DLC0049_01.102	GAMMA GROUP 5 (FISSION)	426
DLC0049_01.103	GAMMA GROUP 6 (FISSION)	402
DLC0049_01.104	GAMMA GROUP 7 (FISSION)	376
DLC0049_01.105	GAMMA GROUP 8 (FISSION)	352
DLC0049_01.106	GAMMA GROUP 9 (FISSION)	326
DLC0049_01.107	GAMMA GROUP 10 (FISSION)	302
DLC0049_01.108	GAMMA GROUP 11 (FISSION)	276
DLC0049_01.109	GAMMA GROUP 12 (FISSION)	252
DLC0049_01.110	GAMMA GROUP 13 (FISSION)	226
DLC0049_01.111	GAMMA GROUP 14 (FISSION)	202
DLC0049_01.112	GAMMA GROUP 15 (FISSION)	176
DLC0049_01.113	GAMMA GROUP 16 (FISSION)	152
DLC0049_01.114	GAMMA GROUP 17 (FISSION)	126
DLC0049_01.115	GAMMA GROUP 18 (FISSION)	102
DLC0049_01.116	GAMMA GROUP 19 (FISSION)	76
DLC0049_01.117	GAMMA GROUP 20 (FISSION)	52
DLC0049_01.118	GAMMA GROUP 21 (FISSION)	26
DLC0049_01.119	COEFFICIENTS FOR FITTED RESULTS	1711
DLC0049_01.120	EDT303 SOURCE PROGRAM (FORTRAN-4)	496
DLC0049_01.121	EDT303 JCL TO EDIT LIBRARY DATA	190
DLC0049_01.122	EDT303 TEST CASE PRINTED OUTPUT	6916

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17. CATEGORIES

J. Gamma Heating and Shield Design
Z. Data.

Keywords: data library, multigroup, neutron transport theory, photon transport, radiation doses, shielding.