NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, 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 OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY 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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SUPERTOG-3 | PSR-0013/04 | Tested | 01-OCT-1975 |

SUPERTOG-4 | PSR-0013/05 | Tested | 01-NOV-1978 |

SUPERTOG-JR | PSR-0013/06 | Tested | 01-JUL-1979 |

Machines used:

Package ID | Orig. computer | Test computer |
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PSR-0013/04 | IBM 370 series | IBM 370 series |

PSR-0013/05 | IBM 360 series | IBM 360 series |

PSR-0013/06 | IBM 370 series | IBM 370 series |

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3. NATURE OF PHYSICAL PROBLEM SOLVED

SUPERTOG accepts nuclear data in either a point by point or parametric representation as specified by ENDF/B. This data is averaged over each specified group width. The explicit assumption is made that the flux per unit lethargy is constant or that a suitable weight function will be supplied by the user. When resonance data is available, resolved and unresolved resonance contributions are calculated and used as specified by input options. Fine group constants such as one-dimensional reaction arrays (absorption, fission, etc.), PN elastic scattering matrices, and inelastic and (n,2n) scattering matrices are generated and placed on tapes in formats suitable for use by GAM-I, GAM-II, ANISN, or DOT.

SUPERTOG-2: Data are accepted in ENDF/B-2 format.

SUPERTOG-3: Data are accepted in ENDF/B-3 format.

SUPERTOG-4: data are accepted in ENDF/B-4 format.

SUPERTOG-JR is an extension of SUPERTOG to generate the energy deposition coefficients and atomic displacement constants due to the following nuclear reactions: elastic and inelastic scattering, (n,zn), (n,gamma), (n,p), and (n,alpha).

SUPERTOG accepts nuclear data in either a point by point or parametric representation as specified by ENDF/B. This data is averaged over each specified group width. The explicit assumption is made that the flux per unit lethargy is constant or that a suitable weight function will be supplied by the user. When resonance data is available, resolved and unresolved resonance contributions are calculated and used as specified by input options. Fine group constants such as one-dimensional reaction arrays (absorption, fission, etc.), PN elastic scattering matrices, and inelastic and (n,2n) scattering matrices are generated and placed on tapes in formats suitable for use by GAM-I, GAM-II, ANISN, or DOT.

SUPERTOG-2: Data are accepted in ENDF/B-2 format.

SUPERTOG-3: Data are accepted in ENDF/B-3 format.

SUPERTOG-4: data are accepted in ENDF/B-4 format.

SUPERTOG-JR is an extension of SUPERTOG to generate the energy deposition coefficients and atomic displacement constants due to the following nuclear reactions: elastic and inelastic scattering, (n,zn), (n,gamma), (n,p), and (n,alpha).

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4. METHOD OF SOLUTION

The single-level Breit-Wigner formalism is used for calculation of cross sections in the resolved resonance region. Cross sections in the unresolved resonance region are computed by taking averages over suitable Porter-Thomas distributions of the neutron and fission widths. Smooth cross sections are calculated by integration of point cross section data given in ENDF/B file 3. Elastic scattering matrices are computed from Legendre coefficients of the scattering angular-distribution data. Inelastic scattering and (n,2n) matrices are computed from excitation functions for individual levels and by using a nuclear evaporation model above the region of resolved levels.

SUPERTOG-JR: For the numerical integration, the Gauss method is mainly used.

The single-level Breit-Wigner formalism is used for calculation of cross sections in the resolved resonance region. Cross sections in the unresolved resonance region are computed by taking averages over suitable Porter-Thomas distributions of the neutron and fission widths. Smooth cross sections are calculated by integration of point cross section data given in ENDF/B file 3. Elastic scattering matrices are computed from Legendre coefficients of the scattering angular-distribution data. Inelastic scattering and (n,2n) matrices are computed from excitation functions for individual levels and by using a nuclear evaporation model above the region of resolved levels.

SUPERTOG-JR: For the numerical integration, the Gauss method is mainly used.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Since fixed, rather than flexible, dimensions are used, it is important to be aware of the maximum values allowed for certain key variables. Examples are - number of groups <=150, number of data points for each reaction type <=4000, and the number of Legendre coefficients <=30.

SUPERTOG-4: Number of data points for each reaction type <= 5000.

SUPERTOG-JR: Number of neutron energy groups <= 100.

Since fixed, rather than flexible, dimensions are used, it is important to be aware of the maximum values allowed for certain key variables. Examples are - number of groups <=150, number of data points for each reaction type <=4000, and the number of Legendre coefficients <=30.

SUPERTOG-4: Number of data points for each reaction type <= 5000.

SUPERTOG-JR: Number of neutron energy groups <= 100.

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6. TYPICAL RUNNING TIME

SUPERTOG-3:Running time varies greatly and is a function, primarily, of the number of groups, the number of resolved resonances, and the length of the elastic scattering matrix. The average time required on IBM 360/91 to generate DLC-2D from ENDF/B-3 data was 2.2 minutes per nuclide.

SUPERTOG-JR: For Fe with 39 energy groups, about 20 CPU minutes are required on FACOM 230/75, of which 5.7 minutes are spent in the newly added routine.

SUPERTOG-3:Running time varies greatly and is a function, primarily, of the number of groups, the number of resolved resonances, and the length of the elastic scattering matrix. The average time required on IBM 360/91 to generate DLC-2D from ENDF/B-3 data was 2.2 minutes per nuclide.

SUPERTOG-JR: For Fe with 39 energy groups, about 20 CPU minutes are required on FACOM 230/75, of which 5.7 minutes are spent in the newly added routine.

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8. RELATED AND AUXILIARY PROGRAMS

The DLC-2 retrieval program retrieves SUPERTOG output from a card image tape written in the ANISN card image format. This program will retrieve data from a maximum of 46 data sets and merge this data onto one data set. It will then, by input option, edit the data, punch cards in either the ANISN or DTF-IV format, or write an unformatted tape for use by ANISN. Another program is available which will merge up to a maximum of four card image tapes written in the GAM-II update format onto a single tape. This program can also take the one-dimensional arrays from one tape and the two-dimensional arrays from another tape and merge this information onto a single tape. The single tape is input to the SUPERTOG version of the GAM-II update program. The GAM-II update program has been modified to accept output from SUPERTOG on either punched cards or magnetic tape.

SUPERTOG-JR: Although the program is available as stand-alone code, it has bee developed as part of the RADHEAT system.

The DLC-2 retrieval program retrieves SUPERTOG output from a card image tape written in the ANISN card image format. This program will retrieve data from a maximum of 46 data sets and merge this data onto one data set. It will then, by input option, edit the data, punch cards in either the ANISN or DTF-IV format, or write an unformatted tape for use by ANISN. Another program is available which will merge up to a maximum of four card image tapes written in the GAM-II update format onto a single tape. This program can also take the one-dimensional arrays from one tape and the two-dimensional arrays from another tape and merge this information onto a single tape. The single tape is input to the SUPERTOG version of the GAM-II update program. The GAM-II update program has been modified to accept output from SUPERTOG on either punched cards or magnetic tape.

SUPERTOG-JR: Although the program is available as stand-alone code, it has bee developed as part of the RADHEAT system.

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Package ID | Status date | Status |
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PSR-0013/04 | 01-OCT-1975 | Tested at NEADB |

PSR-0013/05 | 01-NOV-1978 | Tested at NEADB |

PSR-0013/06 | 01-JUL-1979 | Tested at NEADB |

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PSR-0013/04, included references:

- R.Q. Wright, N.M. Greene, J.L. Lucius, C.W. Craven, Jr.:SUPERTOG, Data Generator - Fine Group Constants and PN Scattering

Matrices from ENDF/B

ORNL-TM-2679 (September 1969).

- D. Steiner:

Analysis of a Bench-Mark Calculation of Tritium Breeding in a

Fusion Reactor Blanket: The United States Contribution

ORNL-TM-4177 (April 1973).

- SUPERTOG-3: A Correction to Subroutine CWAX

NEA CPL Note (December 1973).

- To the User of the Program SUPERTOG-4

NEA CPL Note (September 1976).

PSR-0013/05, included references:

- R.Q. Wright, N.M. Greene, J.L. Lucius, C.W. Craven, Jr.:SUPERTOG, Data Generator - Fine Group Constants and PN Scattering

Matrices from ENDF/B

ORNL-TM-2679 (September 1969).

- D. Steiner:

Analysis of a Bench-Mark Calculation of Tritium Breeding in a

Fusion Reactor Blanket: The United States Contribution

ORNL-TM-4177 (April 1973).

- SUPERTOG-3: A Correction to Subroutine CWAX

NEA CPL Note (December 1973).

- To the User of the Program SUPERTOG-4

NEA CPL Note (September 1976).

PSR-0013/06, included references:

- Y. Taji, T. Okada, K. Minami, S. Miyasaka:SUPERTOG-JR, A Code Generating Transport Group Constants, Energy

Deposition Coefficients and Atomic Displacement Constants with

ENDF/B

JAERI-M 6935 (February 1977).

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Package ID | Computer language |
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PSR-0013/04 | FORTRAN-IV |

PSR-0013/05 | FORTRAN-IV |

PSR-0013/06 | FORTRAN-IV |

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PSR-0013/04

File name | File description | Records |
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PSR0013_04.001 | INFORMATION | 5 |

PSR0013_04.002 | SOURCE PROGRAM (F4) | 10969 |

PSR0013_04.003 | OVERLAY CARDS | 27 |

PSR0013_04.004 | SAMPLE PROBLEM DATA | 4 |

PSR0013_04.005 | JCL | 12 |

PSR0013_04.006 | SAMPLE PROBLEM PRINTED OUTPUT | 1868 |

PSR-0013/05

File name | File description | Records |
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PSR0013_05.001 | SOURCE PROGRAM (F4,EBCDIC) | 10942 |

PSR0013_05.002 | JCL + SAMPLE PROBLEM INPUT DATA (CASE 1) | 19 |

PSR0013_05.003 | JCL + SAMPLE PROBLEM INPUT DATA (CASE 2) | 19 |

PSR0013_05.004 | SAMPLE PROBLEM PRINTED OUTPUT (CASE 1) | 3809 |

PSR0013_05.005 | SAMPLE PROBLEM PRINTED OUTPUT (CASE 2) | 353 |

PSR-0013/06

File name | File description | Records |
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PSR0013_06.001 | INFORMATIONS | 2 |

PSR0013_06.002 | LIBRARY DATA(BCD) | 10167 |

PSR0013_06.003 | SOURCE PROGRAM(F4,EBCDIC) | 13595 |

PSR0013_06.004 | JCL | 21 |

PSR0013_06.005 | INPUT | 10 |

PSR0013_06.006 | OUTPUT | 1057 |

Keywords: Breit-Wigner formula, ENDF/B, absorption, cross sections, elastic scattering, fission, group constants, inelastic scattering, legendre polynomials, matrices, porter-thomas distribution, scattering.