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, 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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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

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.

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.

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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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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CCC-0636/02

File name | File description | Records |
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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 |

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