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CCC-0083 RAID.

RAID, Gamma, Neutron Scattering into Cylindrical or Multibend Duct

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1. NAME OR DESIGNATION OF PROGRAM:  RAID.
Monte Carlo Multibend Shielding Code.
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2. COMPUTERS
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Program name Package id Status Status date
RAID CCC-0083/01 Tested 22-FEB-1990

Machines used:

Package ID Orig. computer Test computer
CCC-0083/01 IBM 7090 IBM 3083
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3. DESCRIPTION OF PROGRAM OR FUNCTION

RAID evaluates the energy, angular distribution, and intensity of either the scattered neutron  or gamma-ray flux that penetrates a straight cylindrical or a multibend duct. A neutron or gamma-ray source may be described with  a set of from 1 to 30 point sources. The energy and angular distribution and the intensity of the scattered flux are calculated  for each set of from 1 to 30 detector points.
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4. METHOD OF SOLUTION

The Monte Carlo method represents a Neumann series solution of the integral transport equation. Included in the  sampling techniques are splitting, Russian Roulette, statistical estimation, and a method of importance sampling in the source angular distribution.
The code provides for the calculation of the energy and angular distribution of the scattered neutron or gamma-ray flux, the total scattered neutron or gamma-ray flux and dose rates, and the unscattered neutron or gamma-ray flux and dose rate.
A library of cross sections which can be easily changed is packaged with the code.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

There are no known restrictions implied by storage allocation or argument range due to  approximations.
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6. TYPICAL RUNNING TIME:
CCC-0083/01
The test case has been executed by NEA-DB on an IBM3083 computer in 0.8 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

The code has been used in the analysis of the gamma radiation environment above a fallout field, where the effect of the air-ground interface is taken into account.
The geometry routine is sufficiently flexible for the description of many of the shield configurations encountered in reactor, weapon, and space shielding.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
CCC-0083/01 22-FEB-1990 Tested at NEADB
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10. REFERENCES:
CCC-0083/01, included references:
- J.A. Moore, J.B. Eggen and F.O. Leopard:
  Monte Carlo Procedure for Analysis of Radiation in Ducts (RAID).
  AFWL-TR 67-9  (August 1967)
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11. MACHINE REQUIREMENTS:
CCC-0083/01
To run the test case included in this package on an IBM 3083, 520K bytes of main storage are required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0083/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
CCC-0083/01
MVS/XA with compiler VS FORTRAN level 2.3.0 (IBM 3083).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Developed by:
                USAF Nuclear Aerospace Research Facility (NARF)
                General Dynamics
                Fort Worth, Texas, 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
CCC-0083/01
File name File description Records
CCC0083_01.001 Information file 97
CCC0083_01.002 RAID source file 5153
CCC0083_01.003 Simulator for SLITE and SLITET 14
CCC0083_01.004 Sample data 687
CCC0083_01.005 JCL used at Data Bank 25
CCC0083_01.006 Sample output by the Data Bank 380
CCC0083_01.007 Sample output by the author 217
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: angular distribution, cylindrical configuration, dose rates, ducts, gamma radiation, neutron flux, radiation doses, shielding.