Computer Programs

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM 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 AUTHOR, MATERIAL, CATEGORIES

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Program name | Package id | Status | Status date |
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SCAP-82 | CCC-0418/01 | Tested | 30-APR-1987 |

Machines used:

Package ID | Orig. computer | Test computer |
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CCC-0418/01 | CDC 7600 | CDC CYBER 740 |

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3. DESCRIPTION OF PROBLEM OR FUNCTION

SCAP solves for radiation transport in complex geometries using the single or albedo scatter point kernel method. The program is designed to calculate the neu- tron or gamma ray radiation level at detector points located within or outside a complex radiation scatter source geometry or a user specified discrete scattering volume. Geometry is describable by zones bounded by intersecting quadratic surfaces within an arbitrary maximum number of boundary surfaces per zone. Anisotropic point sources are describable as pointwise energy dependent distributions of polar angles on a meridian; isotropic point sources may also be specified. The attenuation function for gamma rays is an exponential function on the primary source leg and the scatter leg with a build- up factor approximation to account for multiple scatter on the scat- ter leg. The neutron attenuation function is an exponential function using neutron removal cross sections on the primary source leg and scatter leg. Line or volumetric sources can be represented as a dis- tribution of isotropic point sources, with uncollided line-of-sight attenuation and buildup calculated between each source point and the detector point.

SCAP solves for radiation transport in complex geometries using the single or albedo scatter point kernel method. The program is designed to calculate the neu- tron or gamma ray radiation level at detector points located within or outside a complex radiation scatter source geometry or a user specified discrete scattering volume. Geometry is describable by zones bounded by intersecting quadratic surfaces within an arbitrary maximum number of boundary surfaces per zone. Anisotropic point sources are describable as pointwise energy dependent distributions of polar angles on a meridian; isotropic point sources may also be specified. The attenuation function for gamma rays is an exponential function on the primary source leg and the scatter leg with a build- up factor approximation to account for multiple scatter on the scat- ter leg. The neutron attenuation function is an exponential function using neutron removal cross sections on the primary source leg and scatter leg. Line or volumetric sources can be represented as a dis- tribution of isotropic point sources, with uncollided line-of-sight attenuation and buildup calculated between each source point and the detector point.

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4. METHOD OF SOLUTION

A point kernel method using an ansiotropic or isotropic point source representation is used, line-of-sight material attenuation and inverse square spatial attenuation between the source point and scatter points and the scatter points and de- tector point is employed. A direct summation of individual point source results is obtained.

A point kernel method using an ansiotropic or isotropic point source representation is used, line-of-sight material attenuation and inverse square spatial attenuation between the source point and scatter points and the scatter points and de- tector point is employed. A direct summation of individual point source results is obtained.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The SCAP program is written in complete flexible dimensioning so that no restrictions are imposed on the number of energy groups or geometric zones. The geometric zone description is restricted to zones defined by boun- dary surfaces defined by the general quadratic equation or one of its degenerate forms. The only restriction in the program is that the total program length plus the total data array dimension for small core memory must be less than 150,000 (octal).

The SCAP program is written in complete flexible dimensioning so that no restrictions are imposed on the number of energy groups or geometric zones. The geometric zone description is restricted to zones defined by boun- dary surfaces defined by the general quadratic equation or one of its degenerate forms. The only restriction in the program is that the total program length plus the total data array dimension for small core memory must be less than 150,000 (octal).

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6. TYPICAL RUNNING TIME

The SCAP program computes approximately 200 source point-to scatter point-to detector point calculations per second on the CDC-7600. This running time is essentially independent of the number of energy groups and is only dependent upon the calcu- lation of geometry dependent data.

The SCAP program computes approximately 200 source point-to scatter point-to detector point calculations per second on the CDC-7600. This running time is essentially independent of the number of energy groups and is only dependent upon the calcu- lation of geometry dependent data.

CCC-0418/01

NEA-DB executed the test case included in this package on a CDC CYBER 740 computer in 1564 seconds of CPU time.[ top ]

7. UNUSUAL FEATURES OF THE PROGRAM

The use of a generalized method of determining scatter point densities (general geometry) based on the electron density of the media encountered on a line-of-sight as well as the use of a generalized spherical geometry integration technique over scatter zones defined in a complex geometry are unique features of the program. All input data are read using the free form FIDO input routines which allows free field input of data. The program is written using flexible dimensioning as described in Item 5 above.

The use of a generalized method of determining scatter point densities (general geometry) based on the electron density of the media encountered on a line-of-sight as well as the use of a generalized spherical geometry integration technique over scatter zones defined in a complex geometry are unique features of the program. All input data are read using the free form FIDO input routines which allows free field input of data. The program is written using flexible dimensioning as described in Item 5 above.

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10. REFERENCES

- R.K. Disney, S.L. Zeigler:

"Point Kernel Techniques"

WANL-PR(LL)-034 Volume 6 (August 1970).

- R.G. Soltesz, R.K. Disney, S.L. Zeigler:

"Cross Section Generation and Data Processing Techniques"

WANL-PR(LL)034 Volume 3 (August 1970).

- R.K. Disney, S.L. Zeigler:

"Point Kernel Techniques"

WANL-PR(LL)-034 Volume 6 (August 1970).

- R.G. Soltesz, R.K. Disney, S.L. Zeigler:

"Cross Section Generation and Data Processing Techniques"

WANL-PR(LL)034 Volume 3 (August 1970).

CCC-0418/01, included references:

- R.K. Disney, A.R. McIlvaine and S.E. Bevan:SCAP - Computer Program Description Single Scatter, Albedo Scatter

or Point Kernel Analysis Program in Complex Geometry.

CCC-418/SCAP-82 (April 1980)

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CCC-0418/01

The test case was executed on CDC CYBER 740 in 166,200 (octal) words of CM.[ top ]

CCC-0418/01

NOS 2.5.1 664/650 (CDC CYBER 740).[ top ]

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CCC-0418/01

File name | File description | Records |
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CCC0418_01.001 | Informaton file | 71 |

CCC0418_01.002 | JCL Control Information | 20 |

CCC0418_01.003 | Library conversion program source (FOR-IV) | 20 |

CCC0418_01.004 | Photon Cross Section Library | 855 |

CCC0418_01.005 | SCAP source (FORTRAN IV) | 2382 |

CCC0418_01.006 | Subroutines RFLS,CLEAR,FFREAD (FORTRAN IV) | 173 |

CCC0418_01.007 | Original subroutine FFREAD (FORTRAN IV) | 127 |

CCC0418_01.008 | Sample input data | 312 |

CCC0418_01.009 | Sample output | 4685 |

Keywords: albedo, anisotropic, gamma radiation, isotropic, neutron transport equation, point kernels, point sources, scattering, shielding.