Computer Programs
DLC-0049 ZZ-AIRFEWG.
last modified: 20-MAY-1985 | catalog | categories | new | search |

DLC-0049 ZZ-AIRFEWG.

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

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

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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.