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, MACHINE 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 |
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QADMOD-G | CCC-0396/01 | Tested | 26-FEB-1993 |

Machines used:

Package ID | Orig. computer | Test computer |
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CCC-0396/01 | IBM 3033 | DEC VAX 6000 |

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3. DESCRIPTION OF PROGRAM OR FUNCTION

QAD is the generic designation for a series of point-kernel computer programs designed for estimating the effects of gamma-rays and neutrons that originate in a volume-distributed source. QADMOD is a modified version of the QAD P-5 point-kernel computer program designed to consider only gamma-ray sources. QADMOD-G has new geometry routines, additional source routines, and internal library data which make the program easier to use. Gamma-ray dose rates, energy depositions, and uncollided fluxes may be calculated. Surfaces, defined by quadric equations, are used for a three-dimensional description of the configuration.

QAD is the generic designation for a series of point-kernel computer programs designed for estimating the effects of gamma-rays and neutrons that originate in a volume-distributed source. QADMOD is a modified version of the QAD P-5 point-kernel computer program designed to consider only gamma-ray sources. QADMOD-G has new geometry routines, additional source routines, and internal library data which make the program easier to use. Gamma-ray dose rates, energy depositions, and uncollided fluxes may be calculated. Surfaces, defined by quadric equations, are used for a three-dimensional description of the configuration.

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4. METHOD OF SOLUTION

QADMOD-G calculates gamma-ray fluxes, dose rates, or heating rates at discrete locations within a complex source-geometry configuration by representing a volume-distributed source by a number of point isotropic sources and computing the distances through all regions traversed by the line-of-sight from the source points to a desired receiver point. From these distances and the characteristics of the materials within them, energy- dependent exponential attenuation factors and energy-dependent buildup factors for gamma-rays are applied to calculate the direct gamma-ray dose and the gamma-ray dose with buildup. The responses to individual source points are summed into source-energy groups and recorded. Input data consists of the source distribution and intensity, the physical geometry, and may include tabulations of attenuation coefficients, buildup factor coefficients, and conversion factors.

Each source may be represented by a volume-distributed source or a series of up to 27 000 point sources. The source spectra are assumed to be constant for all volumes. The source may be defined in terms of a cylindrical, a Cartesian, or a spherical-geometry coordinate system.

As many as 500 point isotropic sources defined in terms of a spatial position and power density may be used in point source calculations. Each point source is represented by the same specified energy spectrum.

Shield configurations are represented in terms of a three- dimensional model which is made up of a series of material and void regions. Each region is defined by a previously-described set of surfaces.

QADMOD-G calculates gamma-ray fluxes, dose rates, or heating rates at discrete locations within a complex source-geometry configuration by representing a volume-distributed source by a number of point isotropic sources and computing the distances through all regions traversed by the line-of-sight from the source points to a desired receiver point. From these distances and the characteristics of the materials within them, energy- dependent exponential attenuation factors and energy-dependent buildup factors for gamma-rays are applied to calculate the direct gamma-ray dose and the gamma-ray dose with buildup. The responses to individual source points are summed into source-energy groups and recorded. Input data consists of the source distribution and intensity, the physical geometry, and may include tabulations of attenuation coefficients, buildup factor coefficients, and conversion factors.

Each source may be represented by a volume-distributed source or a series of up to 27 000 point sources. The source spectra are assumed to be constant for all volumes. The source may be defined in terms of a cylindrical, a Cartesian, or a spherical-geometry coordinate system.

As many as 500 point isotropic sources defined in terms of a spatial position and power density may be used in point source calculations. Each point source is represented by the same specified energy spectrum.

Shield configurations are represented in terms of a three- dimensional model which is made up of a series of material and void regions. Each region is defined by a previously-described set of surfaces.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The radiation source is represented by a series of individual point isotropic sources. For gamma-ray calculations, the direct beam component is calculated exactly. The scattered component is calculated using buildup factors. The code is restricted to using dose buildup factors for a single material.

The program limitations include: a single source spectrum, one source volume with up to 30 subvolumes along each major axis or up to 500 point sources, 30 source energy groups, 30 materials, 100 compositions, 250 surface boundaries, 300 shield geometry regions, 15 boundaries per region, and one set of dose buildup factors. There is no limit on the number of detectors per problem. However, only 100 may be saved for stacked problems.

The radiation source is represented by a series of individual point isotropic sources. For gamma-ray calculations, the direct beam component is calculated exactly. The scattered component is calculated using buildup factors. The code is restricted to using dose buildup factors for a single material.

The program limitations include: a single source spectrum, one source volume with up to 30 subvolumes along each major axis or up to 500 point sources, 30 source energy groups, 30 materials, 100 compositions, 250 surface boundaries, 300 shield geometry regions, 15 boundaries per region, and one set of dose buildup factors. There is no limit on the number of detectors per problem. However, only 100 may be saved for stacked problems.

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6. TYPICAL RUNNING TIME

On the IBM 3033, sample problem 1 took 8.13 seconds and sample problem 2 took 8.l9 seconds. In both cases, the time is a total of the compilation, linkage, and go steps.

On the IBM 3033, sample problem 1 took 8.13 seconds and sample problem 2 took 8.l9 seconds. In both cases, the time is a total of the compilation, linkage, and go steps.

CCC-0396/01

NEA-DB ran each of the two test cases included in this package on a DEC VAX 6000-510 computer in less then 1 second of CPU time.[ top ]

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CCC-0396/01, included references:

- J.H. Price and W.G.M. Blattner:Utilization instructions for QADMOD-G

RRA-N7914 (December 1979).

- J.K. Warkentin

"QADMOD-GP Notes"

Informal notes (November 2, 1990)

- J.K. Warkentin :

"Utilization Instructions for QADMOD-GP - A PC Version of

QADMOD-G with Geometric Progression Buildup Factors"

(November 1, 1990)

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

A FORTRAN IV compiler is required. An Assembler language ORNL-written subroutine called TIME is part of the package. The user may choose to write a

routine for TIME.

A FORTRAN IV compiler is required. An Assembler language ORNL-written subroutine called TIME is part of the package. The user may choose to write a

routine for TIME.

CCC-0396/01

VMS V5.4-1 (DEC VAX 6000).[ top ]

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CCC-0396/01

File name | File description | Records |
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CCC0396_01.001 | Information file | 44 |

CCC0396_01.002 | JCL to execute QADMODG on IBM computer | 16 |

CCC0396_01.003 | JCL and control information | 7 |

CCC0396_01.004 | QADMODG FORTRAN source program | 1664 |

CCC0396_01.005 | TIME ASSEMBLY language routine (IBM version) | 28 |

CCC0396_01.006 | Sample input problem 1 | 64 |

CCC0396_01.007 | Sample input problem 2 | 46 |

CCC0396_01.008 | Sample output problem 1 | 261 |

CCC0396_01.009 | Sample output problem 2 | 906 |

Keywords: dose rates, flux distribution, gamma radiation, neutron flux, point kernels.