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CCC-0120 SPACETRAN.

SPACETRAN, Radiation Leakage from Cylinder with ANISN Flux Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  SPACETRAN.
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2. COMPUTERS
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Program name Package id Status Status date
SPACETRAN CCC-0120/01 Tested 01-AUG-1974

Machines used:

Package ID Orig. computer Test computer
CCC-0120/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

SPACETRAN is designed to calculate the energy-dependent total flux or some proportional quantity such as kerma, due to the radiation leakage from the surface of a right-circular cylinder at detector positions located at arbitrary distances from the surface. The assumptions are made that the radiation emerging from the finite cylinder has no spatial dependence and that a vacuum surrounds the cylinder.
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4. METHOD OF SOLUTION

There are three versions of the program in the code package.
SPACETRAN-I uses the surface angular fluxes calculated by the discrete ordinates SN code ANISN, as input.
SPACETRAN-II assumes that the surface angular flux for all energies  can be represented as a function (COS(PHI))**N, where PHI is the angle between surface outward normal and radiation direction, and N  is an integer specified by the user.
For both versions the energy group structure and the number and location of detectors is arbitrary. The flux (or response function)  for a given energy group at some detection point is computed by summing the contributions from each surface area element over the entire surface. The surface area elements are defined by input data. SPACETRAN-III uses surface angular fluxes from DOT-3.
SPACETRAN-I handles contributions either from a cylinder 'end' or 'side', so the total contributions must be obtained by adding the results of separate end and side runs. ANISN angular fluxes are specified for discrete directions. In general, the direction between the detector and contributing area will not exactly coincide with one of these discrete directions. In this case, the ANISN angular flux for the 'closest' discrete direction is used to approximate the contribution to the detector.
SPACETRAN-II handles contributions from both the side and end of a cylinder in a single run. Since the assumed angular distribution is  specified by a continuous function, it is not necessary to perform the angle selection described above.
For each detector specified, both versions compute the flux and a response proportional to flux in each energy group and also compute  the sum of these quantities over all energy groups.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

There are limitations on the dimensions of certain arrays, but these dimensions can probably be increased somewhat to meet the user's requirements.
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6. TYPICAL RUNNING TIME

Estimated running time of the packaged sample  problem - 1 minute.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
CCC-0120/01 01-AUG-1974 Tested at NEADB
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10. REFERENCES

- S.N. Cramer and M. Solomito:
  'SPACETRAN - A Code to Calculate Dose at Detectors at Various
  Distances from the Surface of a Cylinder.'
  ORNL-TM-2592 (June 1969).
- Informal notes added 9/73.
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0120/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED

The
code is operable on the IBM 360/75-91 using OS-360 with FORTRAN-H compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

S.N. Cramer and M. Solomito

Neutron Physics Division
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U.S.A.
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16. MATERIAL AVAILABLE
CCC-0120/01
File name File description Records
CCC0120_01.001 SPACETRAN-1 SOURCE PROGRAM (FORTRAN) 149
CCC0120_01.002 SPACETRAN-1 SAMPLE PROBLEM 33
CCC0120_01.003 SPACETRAN-2 SOURCE PROGRAM (FORTRAN) 133
CCC0120_01.004 SPACETRAN-2 SAMPLE PROBLEM 8
CCC0120_01.005 SPACETRAN-3 SOURCE PROGRAM (FORTRAN) 951
CCC0120_01.006 SPACETRAN-3 SAMPLE PROBLEM 16
CCC0120_01.007 SPACETRAN-3 INPUT FOR DOT-3 (ID=RZ6) 231
CCC0120_01.008 SPACETRAN-3 JCL 5
CCC0120_01.009 SPACETRAN-1 OUTPUT OF SAMPLE PROBLEM 127
CCC0120_01.010 SPACETRAN-2 OUTPUT OF SAMPLE PROBLEM 42
CCC0120_01.011 SPACETRAN-3 OUTPUT OF SAMPLE PROBLEM 103
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • J. Gamma Heating and Shield Design

Keywords: angular distribution, cylinders, doses, neutron flux, radiation effects.