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NESC0567 3DB

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:  3DB
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2. COMPUTERS
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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 PROBLEM 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 -
   (a) compute keff and perform criticality searches on time
       absorption, reactor composition, and reactor dimensions by
       means of either a flux or an adjoint model,
   (b) compute material burnup using a flexible material shuffling
       scheme, and
   (c) compute flux distributions for an arbitrary extraneous
       source.
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4. METHOD OF SOLUTION

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 AND 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. MACHINE 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. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:            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
   360           W. Mroz
                 Applied Mathematics Division
                 Argonne National Laboratory
                 9700 South Cass Avenue
                 Argonne, Illinois  60439
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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.