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 AUTHORS, MATERIAL, CATEGORIES

[ top ]

[ top ]

To submit a request, click below on the link of the version you wish to order.
Only liaison officers are authorised to submit online requests. Rules for requesters are
available here.

Program name | Package id | Status | Status date |
---|---|---|---|

DTF-4 | NESC0209/01 | Tested | 01-DEC-1976 |

DTF-4 | NESC0209/02 | Tested | 01-NOV-1967 |

DTF-TRACA | NESC0209/07 | Tested | 25-MAY-1981 |

Machines used:

Package ID | Orig. computer | Test computer |
---|---|---|

NESC0209/01 | CDC CYBER 174 | CDC CYBER 174 |

NESC0209/02 | IBM 360 series | IBM 360 series |

NESC0209/07 | UNIVAC 1110 | UNIVAC 1110 |

[ top ]

3. DESCRIPTION OF PROBLEM OR FUNCTION

The linear, time-independent, Boltzmann equation for particle transport is solved for the energy space, and angular dependence of the particle distribution in one- dimensional slabs, cylinders, and spheres. Independent source or eigenvalue (multiplication, time-absorption, element concentration, zone thickness or system dimension) problems are solved subject to vacuum, reflective, or periodic boundary conditions. A complete energy-transfer scattering matrix is allowed for each Legendre component of the scattering cross section matrices.

The linear, time-independent, Boltzmann equation for particle transport is solved for the energy space, and angular dependence of the particle distribution in one- dimensional slabs, cylinders, and spheres. Independent source or eigenvalue (multiplication, time-absorption, element concentration, zone thickness or system dimension) problems are solved subject to vacuum, reflective, or periodic boundary conditions. A complete energy-transfer scattering matrix is allowed for each Legendre component of the scattering cross section matrices.

[ top ]

4. METHOD OF SOLUTION

Energy dependence is treated by the multigroup approximation and angular dependence by a general discrete ordinates approximation. Anisotropic scattering is approximated by a truncated spherical harmonics expansion of the scattering kernel. Within-group scattering and up-scattering (if any) iteration processes are accelerated by system-wide renormalization procedures. Approximations and iterative cycles are described in detail in the DTF4 report.

Energy dependence is treated by the multigroup approximation and angular dependence by a general discrete ordinates approximation. Anisotropic scattering is approximated by a truncated spherical harmonics expansion of the scattering kernel. Within-group scattering and up-scattering (if any) iteration processes are accelerated by system-wide renormalization procedures. Approximations and iterative cycles are described in detail in the DTF4 report.

[ top ]

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The variable dimensioning capability of FORTRAN IV has been utilized so that any combination of number of groups, number of spatial intervals, size of angular quadrature, etc., can be used that will fit within the total core storage available to a user. The code itself requires about 8000 words, but it can be shortened by deleting certain subroutines which perform optional calculations.

The variable dimensioning capability of FORTRAN IV has been utilized so that any combination of number of groups, number of spatial intervals, size of angular quadrature, etc., can be used that will fit within the total core storage available to a user. The code itself requires about 8000 words, but it can be shortened by deleting certain subroutines which perform optional calculations.

[ top ]

[ top ]

7. UNUSUAL FEATURES OF THE PROGRAM

General anisotropic scattering capability is provided in each of the three geometries, up- scattering convergence acceleration is used, an optional group- and point-wise convergence test is available, and a neutron conserving negative flux correction routine is used.

General anisotropic scattering capability is provided in each of the three geometries, up- scattering convergence acceleration is used, an optional group- and point-wise convergence test is available, and a neutron conserving negative flux correction routine is used.

[ top ]

[ top ]

Package ID | Status date | Status |
---|---|---|

NESC0209/01 | 01-DEC-1976 | Tested at NEADB |

NESC0209/02 | 01-NOV-1967 | Tested at NEADB |

NESC0209/07 | 25-MAY-1981 | Tested at NEADB |

[ top ]

10. REFERENCES

- K. D. Lathrop, DTF-IV, A FORTRAN-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering, LA-3373, July 15, 1965.

- B. G. Carlson, W. J. Worlton, W. Guber and M. Shapiro, DTF Users Manual, UNC Phys/Math 3321, Volumes I and II, 1963.

- K. D. Lathrop, GAMLEG, CCA-115, Nuclear Science and Engineering, Vol. 24, February 1966.

- R. L. Brunnenmeyer and R. A. Mickle, DTF-IV GE-625 Version (NE101) Users Notes, Bechtel Note, July 1968.

- R. Douglas O'Dell and Raymond E. Alcouffe: Transport Calculations for Nuclear Analyses: Theory and Guidelines for Effective Use of Transport Codes LA-10983-MS and UC-32 (September 1987)

- K. D. Lathrop, DTF-IV, A FORTRAN-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering, LA-3373, July 15, 1965.

- B. G. Carlson, W. J. Worlton, W. Guber and M. Shapiro, DTF Users Manual, UNC Phys/Math 3321, Volumes I and II, 1963.

- K. D. Lathrop, GAMLEG, CCA-115, Nuclear Science and Engineering, Vol. 24, February 1966.

- R. L. Brunnenmeyer and R. A. Mickle, DTF-IV GE-625 Version (NE101) Users Notes, Bechtel Note, July 1968.

- R. Douglas O'Dell and Raymond E. Alcouffe: Transport Calculations for Nuclear Analyses: Theory and Guidelines for Effective Use of Transport Codes LA-10983-MS and UC-32 (September 1987)

NESC0209/01, included references:

- C. Ahnert:The Neutron Transport Code DTF-Traca User's Manual and Input Data. J.E.N.448,

Sp ISSN 0081-3397 (March 1979).

- K.D. Lathrop:

DTF-IV, A Fortran-IV program for Solving the Multigroup Transport Equation with

Anisotropic Scattering, LA-3373, UC-32, Mathematics and Computers TID-4500

(45th Ed.) (July 1965)

- K.D. Lathrop, B.G. Carlson:

Discrete Ordinates Angular Quadrature of the Neutron Transport Equation

LA-3186, UC-32, Mathematics and Computers TID-4500 (36th Ed.) September 1964

- K.D. Lathrop:

GAMLEG - A Fortran Code to Produce Multigroup Cross Sections for Photon

Transport Calculations

LA-3267 (April 1965)

- B.G. Carlson et al.:

DTF Users Manual, UNC Phys/Math-3321, Vol. I and II (November 1963)

- A.K. Jena:

DTF (Modified), FRG/01150/RP-218 (February 1982)

NESC0209/02, included references:

- C. Ahnert:The Neutron Transport Code DTF-Traca User's Manual and Input Data. J.E.N.448,

Sp ISSN 0081-3397 (March 1979).

- K.D. Lathrop:

DTF-IV, A Fortran-IV program for Solving the Multigroup Transport Equation with

Anisotropic Scattering, LA-3373, UC-32, Mathematics and Computers TID-4500

(45th Ed.) (July 1965)

- K.D. Lathrop, B.G. Carlson:

Discrete Ordinates Angular Quadrature of the Neutron Transport Equation

LA-3186, UC-32, Mathematics and Computers TID-4500 (36th Ed.) September 1964

- K.D. Lathrop:

GAMLEG - A Fortran Code to Produce Multigroup Cross Sections for Photon

Transport Calculations

LA-3267 (April 1965)

- B.G. Carlson et al.:

DTF Users Manual, UNC Phys/Math-3321, Vol. I and II (November 1963)

- A.K. Jena:

DTF (Modified), FRG/01150/RP-218 (February 1982)

NESC0209/07, included references:

- C. Ahnert:The Neutron Transport Code DTF-Traca User's Manual and Input Data. J.E.N.448,

Sp ISSN 0081-3397 (March 1979).

- K.D. Lathrop:

DTF-IV, A Fortran-IV program for Solving the Multigroup Transport Equation with

Anisotropic Scattering, LA-3373, UC-32, Mathematics and Computers TID-4500

(45th Ed.) (July 1965)

- K.D. Lathrop, B.G. Carlson:

Discrete Ordinates Angular Quadrature of the Neutron Transport Equation

LA-3186, UC-32, Mathematics and Computers TID-4500 (36th Ed.) September 1964

- K.D. Lathrop:

GAMLEG - A Fortran Code to Produce Multigroup Cross Sections for Photon

Transport Calculations

LA-3267 (April 1965)

- B.G. Carlson et al.:

DTF Users Manual, UNC Phys/Math-3321, Vol. I and II (November 1963)

- A.K. Jena:

DTF (Modified), FRG/01150/RP-218 (February 1982)

[ top ]

[ top ]

Package ID | Computer language |
---|---|

NESC0209/01 | FORTRAN-IV |

NESC0209/02 | FORTRAN-IV |

NESC0209/07 | FORTRAN-V (UNIVAC) |

[ top ]

[ top ]

[ top ]

15. NAME AND ESTABLISHMENT OF AUTHORS

6600 K. D. Lathrop

Los Alamos Scientific Laboratory

P. O. Box 1663

Los Alamos, New Mexico 87545

625 R. L. Brunnenmeyer and R. A. Mickle

Bechtel Corporation

50 Beale Street

San Francisco, California 94119

360 G. J. Duffy

Applied Mathematics Division

Argonne National Laboratory

9700 South Cass Avenue

Argonne, Illinois 60439

6600 K. D. Lathrop

Los Alamos Scientific Laboratory

P. O. Box 1663

Los Alamos, New Mexico 87545

625 R. L. Brunnenmeyer and R. A. Mickle

Bechtel Corporation

50 Beale Street

San Francisco, California 94119

360 G. J. Duffy

Applied Mathematics Division

Argonne National Laboratory

9700 South Cass Avenue

Argonne, Illinois 60439

[ top ]

NESC0209/01

File name | File description | Records |
---|---|---|

NESC0209_01.001 | INFORMATION | 3 |

NESC0209_01.002 | SOURCE PROGRAM | 2073 |

NESC0209_01.003 | SAMPLE PROBLEM INPUT DATA | 320 |

NESC0209_01.004 | SAMPLE PROBLEM PUNCHED OUTPUT | 146 |

NESC0209_01.005 | SAMPLE PROBLEM PRINTED OUTPUT | 3085 |

NESC0209/02

File name | File description | Records |
---|---|---|

NESC0209_02.002 | SOURCE & 2 SAMPLE PROBLEMS 360/65 | 2227 |

NESC0209_02.003 | PRINTED OUTPUT | 2929 |

NESC0209_02.004 | PUNCHED OUTPUT | 201 |

NESC0209_02.005 | DATA LIBRARY (BINARY) | 616 |

NESC0209/07

File name | File description | Records |
---|---|---|

NESC0209_07.001 | INFORMATION FILE | 8 |

NESC0209_07.002 | SOURCE + DATA | 2247 |

NESC0209_07.003 | PRINTED OUTPUT | 457 |

Keywords: Boltzmann equation, anisotropic scattering, buckling, criticality searches, cross sections, cylinders, multigroup, multiplication factors, neutron transport equation, one-dimensional, slabs, spheres, transport theory.