last modified: 01-OCT-1974 | catalog | categories | new | search |

NESC0567 3-DB.

3-DB, 3-D MultiGroup Diffusion, X-Y-Z, R-Theta-Z, Triangular-Z Geometry, Fast Reactor Burnup

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1. NAME OR DESIGNATION OF PROGRAM

3-DB

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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
3-DB NESC0567/02 Tested 01-OCT-1974

Machines used:

Package ID Orig. computer Test computer
NESC0567/02 IBM 370 series IBM 370 series
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3. DESCRIPTION OF PROGRAM OR FUNCTION

3DB is a three-dimensional (x-y-z, r-theta-z, triangular-z) multigroup diffusion code for use in detailed fast-reactor criticality and burnup analysis. The code can be used to

  1. compute keff and perform criticality searches on time absorption, reactor composition, and reactor dimensions by means of either a flux or an adjoint model,

  2. compute material burnup using a flexible material shuffling scheme, and

  3. compute flux distributions for an arbitrary extraneous source.

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4. METHODS

Eigenvalues are computed by standard source-iteration techniques. Group rebalancing and successive overrelaxation with line inversion are used to accelerate convergence. Adjoint solutions are obtained by inverting the input data and redefining the source terms. Material burnup is by reactor zone. The burnup rate is determined by the zone and energy-averaged cross sections which are recomputed after each time-step. The isotopic chains, which can contain any number of isotopes are formed by the user. The code does not contain built- in or internal chains.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Since variable dimensioning is employed, no simple bounds can be stated.

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6. TYPICAL RUNNING TIME

A keff calculation with a 20 x 20 x 20 mesh using 2 energy groups requires approximately 30 minutes on a UNIVAC1108. Each successive burnup time-step takes about a quarter of the above time. On an IBM360/195 compilation and link edit require about 1 minute and execution about 7 minutes for the sample problem with 10 x 10 x 10 mesh using 2 zones and 2 energy groups.

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7. UNUSUAL FEATURES OF THE PROGRAM

The input data are arranged so the code can be used easily for keff and search calculations without burdening the user with burnup parameters.

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8. RELATED OR AUXILIARY PROGRAMS

The format of the input data (e.g. cross sections, geometry, and composition specifications) is compatible with the one- and two-dimensional transport codes DTF4 (NESC Abstract 209) and 2DF (NESC Abstract 173), the perturbation code PERT5, the one-dimensional cross section generating code 1DX (NESC Abstract 374), and the two-dimensional diffusion burnup code 2DB (NESC Abstract 325). All six codes use the same input module.

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9. STATUS
Package ID Status date Status
NESC0567/02 01-OCT-1974 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).

  • 2DF, A Two-dimensional Transport Code Developed at the Los Alamos Scientific Laboratory, (unpublished). - R.W. Hardie and W.W. Little, Jr., PERT-V, A Two-dimensional Perturbation Code for Fast Reactor
    Analysis, BNWL-1162 (September 1969).

  • R.W. Hardie and W.W. Little, Jr.,
    1DX, 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).

NESC0567/02, included references:
- R.W. Hardie and W.W. Little, Jr.:
  A Three-Dimensional Diffusion Theory Burnup Code
  BNWL-1264 (March 1970).
- ETIME,ETIMEF,SETDR Descriptions, excerpt from CSCXRJE/CRJE
  Reference, Vol. 2, Library Elements
  E00003-02-00 (April 1971).
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11. HARDWARE REQUIREMENTS

65K word  memory and 11  peripheral storage
devices (UNIVAC1108), 500K  bytes and same number  of mass storage
units (IBM360)

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0567/02 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS

EXEC8 (UNIVAC1108), OS/360 (IBM360).

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Due to differences in word size, the IBM version uses double precision. In addition, certain I/O routines from the UNIVAC library had to be written in FORTRAN for the IBM version.

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15. NAME AND ESTABLISHMENT OF AUTHORS

   1108          R. W. Hardie and W. W. Little, Jr.

                 Hanford Engineering Development Laboratory

                 Westinghouse Hanford Company

                 P. O. Box 1970

                 Richland, Washington  99352, USA

   360           W. Mroz

                 Applied Mathematics Division

                 Argonne National Laboratory

                 9700 South Cass Avenue

                 Argonne, Illinois  60439, USA

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16. MATERIAL AVAILABLE
NESC0567/02
File name File description Records
NESC0567_02.001 SOURCE PROGRAM (F4) 3804
NESC0567_02.002 SAMPLE CASE DATA 76
NESC0567_02.003 JCL 30
NESC0567_02.004 SAMPLE CASE PRINTED OUTPUT 644
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, criticality, diffusion equations, fast reactors, multigroup, r-theta-z, three-dimensional, triangular-z, x-y-z.