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NESC0374 1-DX.

1-DX, 1-D Diffusion for Fast Reactor MultiGroup Cross-Sections, Group Constant Collapsing

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1. NAME OR DESIGNATION OF PROGRAM

1-DX

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2. COMPUTERS
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Program name Package id Status Status date
1-DX NESC0374/03 Tested 01-DEC-1972
1-DX NESC0374/04 Tested 01-JUL-1973

Machines used:

Package ID Orig. computer Test computer
NESC0374/03 IBM 370 series IBM 370 series
NESC0374/04 UNIVAC 1106 UNIVAC 1106
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3. DESCRIPTION OF PROGRAM OR FUNCTION

1-DX is a multipurpose, one-dimensional diffusion code for generating cross sections to be used in fast reactor analyses. The code is designed to

  1. compute and punch resonance shielded cross sections using data in the Russian (see reference 2) format,

  2. compute and punch group-collapsed microscopic and/or macroscopic cross sections averaged over the spectrum in any specified zone, and

  3. compute keff and perform criticality searches on time absorption, material concentrations, zone dimensions, and buckling using either a flux or an adjoint model.

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4. METHODS

Resonance shielded cross sections are calculated using data (infinite dilution cross sections and resonance shielding factors) in the Russian format. Interpolation schemes are used to compute shielding factors applicable to specific compositions. A flux iteration option for computing the elastic removal cross section is also included. Group-collapsed cross sections by reactor zone are calculated using flux weighting. The eigenvalue and spatial flux profiles are computed using standard source-iteration techniques. Convergence is accelerated using fission source overrelaxation. 1DX will also accept input cross sections in the DTF format (i.e., resonance shielded cross sections).

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

1-DX uses variable dimensioning to make maximum use of existing core storage. All subscripted variables are stored in one array dimensioned to 35,000 on the UNIVAC1108. Allocation is dynamic in the IBM version.

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6. TYPICAL RUNNING TIME

A representative 26-group problem with 30 spatial intervals using data in the Russian format requires about 50 seconds on a UNIVAC1108. If the cross section data is already in the DTF format, the same problem would require about 5 seconds. The sample problem requires 12 seconds of CPU time on an IBM370/195.

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8. RELATED OR AUXILIARY PROGRAMS

The format of the input data (e.g., flux dumps, geometry and composition specifications, etc.) is compatible with Los Alamos one- and two-dimensional transport codes DTF4 (NESC Abstract 209) and 2DF (NESC Abstract 173), the BNW two-dimensional burnup code 2DB (NESC Abstract 325), and the BNW perturbation code PERT4 (NESC Abstract 304). The computer code ETOX will prepare cross section data in the Russian format from the ENDF/B data tape. PUPX is an auxiliary program that prints, updates, and punches cross section data in the Russian format using a binary tape.

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9. STATUS
Package ID Status date Status
NESC0374/03 01-DEC-1972 Tested at NEADB
NESC0374/04 01-JUL-1973 Tested at NEADB
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10. REFERENCES
  • I.I. Bondarenko, et al.: Group Constants for Nuclear Reactor Calculations, Consultants Bureau, New York, 1964.

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

  • 2DF, A Two-dimensional Transport Code from the Los Alamos Scientific Laboratory (unpublished).

  • R.W. Hardie and W.W. Little, Jr.: PERT-IV, A Two-dimensional Perturbation Code in FORTRAN-IV BNWL-409, April 1967.

  • R.E. Schenter, J.L. Baker, and R.B. Kidman: ETOX, A Code to Calculate Group Constants for Nuclear Reactor Calculations BNWL-1002, May 1969.

NESC0374/03, included references:
- R.W. Hardie and W.W. Little, Jr.:
  1-DX, A One-dimensional Diffusion Code for Generating Effective
  Nuclear Cross Sections
  BNWL-954 (March 1969).
- W.W. Little, Jr. and R.W. Hardie:
  2DB User's Manual, Revision 1
  BNWL-831, Rev.1 (February 1969).
NESC0374/04, included references:
- R.W. Hardie and W.W. Little, Jr.:
  1-DX, A One-dimensional Diffusion Code for Generating Effective
  Nuclear Cross Sections
  BNWL-954 (March 1969).
- W.W. Little, Jr. and R.W. Hardie:
  2DB User's Manual, Revision 1
  BNWL-831, Rev.1 (February 1969).
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11. HARDWARE REQUIREMENTS

65K memory and 7 peripheral storage devices (UNIVAC1108), 145K and maximum of 8 storage devices (IBM360,370).

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0374/03 FORTRAN-IV
NESC0374/04 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS

OS/360,370 (IBM360,370).

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15. NAME AND ESTABLISHMENT OF AUTHORS

   1108          R. W. Hardie
                 Pacific Northwest Laboratories
                 Battelle
                 P. O. Box 999, USA
                 Richland, Washington  99352
   360,370       H. Henryson, II
                 Applied Physics Division
                 Argonne National Laboratory
                 9700 South Cass Avenue
                 Argonne, Illinois  60439 USA

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16. MATERIAL AVAILABLE
NESC0374/03
File name File description Records
NESC0374_03.001 1-DX SOURCE PROGRAMME 3018
NESC0374_03.002 DD,OVERLAY CARDS+SAMPLE INPUT 452
NESC0374_03.003 AUXILIARY ROUTINE PUPX SOURCE 216
NESC0374_03.004 SAMPLE OUTPUT OF 1-DX 1177
NESC0374/04
File name File description Records
NESC0374_04.001 SOURCE PROGRAM (FORTRAN) + SAMPLE INPUT 1208
NESC0374_04.002 SAMPLE OUTPUT 1110
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems

Keywords: criticality searches, cross sections, diffusion, fast reactors, iterative methods, one-dimensional.