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CCC-0636 ISO-PC.

ISO-PC, X-Ray, Gamma-Bremsstrahlung Dose-Rates

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1. NAME OR DESIGNATION OF PROGRAM:  ISO-PC 2.1.
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2. COMPUTERS
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Program name Package id Status Status date
ISO-PC2.1 CCC-0636/02 Tested 24-NOV-2000

Machines used:

Package ID Orig. computer Test computer
CCC-0636/02 IBM PC PC Pentium III 500,Linux-based PC,IBM RISC6000 WS
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3. DESCRIPTION OF PROGRAM OR FUNCTION

ISO-PC is a revision to the CCC-0079/ISOSHLD-II program. It calculates dose rates from the decay of radionuclides at the exterior of simple geometric shapes. The dose rates from X-rays, gamma-rays and bremsstrahlung radiation are  computed. The portion of the program which computes fission product  inventories (RIBD) has been removed. The ISO-PC program is strictly  a shielding code for simple arrangements of source and shields.
Version 2.1, which replaced Version 1.98 in November 1996, contains  several changes and improvements:
1) three new geometries were added for follow cylinders
2) maximum number of shield regions increased from 5 to 6
3) the DELR parameter is now computed internally
4) several nuclides were added to the library
5) the definition of ICONC was expanded to include mass
   concentrations
6) new NAMELIST variables were added to allow input in SI units
   with standard prefix multipliers.
SOURCE AND SHIELD GEOMETRIES
  1.  Point source with slab shields
  2.  Line source with slab shields
  3.  Sphere with spherical or slab shields
  4.  Truncated cone with slab shields
  5.  Infinite slab or infinite plane with infinite slab shields
  6.  Flat disc with slab shields
  7.  Cylinder with cylindrical or slab shields or a combination of
      one cylindrical shield with two slab shields and the region
      between
  8.  End of a cylinder with slab shields
  9.  Rectangular solid with slab shields
10.  Annular cylindrical source with cylindrical and slab shields
SHIELD MATERIALS
  1.  At most 5 shield regions, including the source
  2.  At most 45 shield materials may be specified for each region
  3.  User must specify which region to use for buildup factors
      SOURCE REGION
  1.  Specify source strength as the total in the source region or
      a uniform concentration
  2.  Specify source strength using library of 535 nuclides or give
      photons/sec at specific energies
MISCELLANEOUS
  1.  30 energy groups for photons from 10 KeV to 10 MeV
  2.  Final dose rate as exposure rate or dose equivalent rate
  3.  Use up to 40 dose points (different distances from source)
      in a single case
  4.  Each run may have multiple cases
  5.  Use SI or traditional units for activity or dose rate
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4. METHOD OF SOLUTION

The photon spectrum for the source region is computed for a fixed energy mesh from the library of photon data. Bremsstrahlung is computed from the library of electron data using tables of bremsstrahlung emission at selected atomic numbers and energies.
The point source attenuation "kernel" (buildup factor times attenuation factor times geometry factor) is integrated over the source region for as many as 30 energy groups. Low energy (less than 100 KeV) buildup factors are computed from a table of values stored  in the data library. Higher energy buildup is computed from Taylor coefficients.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The bremsstrahlung calculation does not distinguish between internal conversion electrons, beta decay, or positron emission. All the electron data is treated as (allowed) beta decay. The attenuation and buildup calculation does not use the recent data found in ANSI/ANS-6.4.3-1991. The differences are small for all materials except water. For water, the newer data predicts much smaller buildup.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
CCC-0636/02 24-NOV-2000 Tested at NEADB
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10. REFERENCES:
CCC-0636/02, included references:
- P.D. Rittmann:
  Notes for Users of ISO-PC Version 2.1 (February 1996)
- P.D. Rittmann:
  Summary of Changes to ISO-PC Version 2.1 (1996)
- P.D. Rittmann:
  ISO-PC Version 2.1 Summary (1996)
- P.D. Rittmann:
  ISO-PC Version 1.98 - User's Guide
  WHC-SD-WM-UM-030 Rev. 0 (1995)
- G.L. Simmons et al.:
  ISOSHLD-II: Code Revision to Include Calculation of Dose Rate
  from Shielded Bremsstrahlung Sources
  BNWL-236-SUP1 (1967)
- R.L. Engle, J. Greenborg, and N.M. Hendrickson:
  ISOSHLD - A Computer Code for General Purpose Isotope Shielding
  Analysis
  BNWL-236 (1966)
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0636/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

ISO-PC 2.1 has been compiled using Lahey F95 and MS DVF under DOS/Windows 98; g77 under linux and xlf under aix 3.4.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

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

Developed by:
                Flour Daniel Northwest (formerly Westinghouse
                Hanford Company)
                Richland, Washington
                United States
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16. MATERIAL AVAILABLE
CCC-0636/02
File name File description Records
ISOPC.INF NEA DB information file 4900
SUMMARY.TXT Summary description and doc of the code 10879
README.TXT Operating instructions 23146
RI.BAT Batch file to run multiple cases (DOS) 1403
ISO-PC.F Main fortran source 66564
ISO-CTRL.F Ancillary routines fortran source 76108
ISO-MISC.F Ancillary routines fortran source 19620
ISO-BLOK.F Block data fortran source 51127
NEADB.F NEA-DB routines fortran source 4756
BLANK.CMN Common blocks 6299
BREMS.CMN Common blocks 2900
CCC_636_2_V1.PDF Documentation file 11704871
CCC_636_2_V2.PDF ISO-PC Version 1.98 documentation 243984
CCC_636_2_V3.PDF ISO-PC Version 2.1 documentation 78700
ISO-PC.LIB Library file 140539
ISO-NUC.LST List of nuclides in library file 30396
CSSR.IN Sample input case from 1.98 manual,corrected 790
CSSR.OUT Output from file CSSR.IN 28056
CSSR.SUM Output from file CSSR.IN 447
PT-6.IN Point source test case input 3002
PT-6.OUT Output from file PT-6.IN 50145
PT-6.SUM Output from file PT-6.IN 2054
SAMPLE.IN Sample input case for Version 2.1 650
SAMPLE.OUT Output from file SAMPLE.IN 24294
SAMPLE.SUM Output from file SAMPLE.IN 472
TST-PM.IN Sample input from BNWL-236-SUP1 (Promethium) 2900
TST-PM.OUT Output from file TST-PM.IN 151954
TST-PM.SUM Output from file TST-PM.IN 2436
TST-SR.IN Sample input from BNWL-236-SUP1 (Strontium) 3207
TST-SR.OUT Output from file TST-SR.IN 155545
TST-SR.SUM Output from file TST-SR.IN 2561
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17. CATEGORIES
  • J. Gamma Heating and Shield Design

Keywords: bremsstrahlung, dose rates, gamma radiation, shielding, x-rays.