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NESC0209 DTF-4

DTF-4, 1-D MultiGroup Time-Independent Boltzmann Equation, Slab, Cylindrical, Spherical Geometry, Sn-Method, Pl-Method

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1. NAME OR DESIGNATION OF PROGRAM:  DTF-4
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2. COMPUTERS
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
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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.
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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.
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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.
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6. TYPICAL RUNNING TIME

The IBM360 version took 3 minutes to compile and execute the sample problem.
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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.
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8. RELATED AND AUXILIARY PROGRAMS

The code is a major revision of the DTF code. The report GAMLEG (reference 3) provides cross sections for photon transport problems in a form suitable for input to DTF4.
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9. STATUS
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
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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)
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)
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11. MACHINE REQUIREMENTS

No disks or tapes are used. A clock is used but, by removing a few program statements, this requirement can be eliminated.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0209/01 FORTRAN-IV
NESC0209/02 FORTRAN-IV
NESC0209/07 FORTRAN-V (UNIVAC)
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/360 (IBM360), and SCOPE (CDC6600).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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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
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16. MATERIAL AVAILABLE
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
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17. CATEGORIES
  • C. Static Design Studies

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