NEA-1506 DPOL3D.

DPOL3D, 2 Group, 3-D Core Transients and Steady State

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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

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1. NAME OR DESIGNATION OF PROGRAM: DPOL3D.

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2. COMPUTERS

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Program name	Package id	Status	Status date
DPOL3D	NEA-1506/01	Arrived	22-MAR-2001

Machines used:

Package ID	Orig. computer	Test computer
NEA-1506/01	CRAY family

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3. DESCRIPTION OF PROGRAM OR FUNCTION

DPOL3D is a two group three dimensional coarse-mesh diffusion code for steady state and dynamic  neutronic full core problems.
DPOL3D is a purely neutron kinetics code, it doesn't perform burnup  or fixed sources calculations.
Anyway it is a very general code well suited for LWR criticality or  time-dependent problems with Max. power errors under 7% for steady state calculations and under 10% for the time-dependent ones.
Field of validity:
Transients with time constants of order of few days , such as Xenon variations, or of months , such as fuel evolutions, or transients highly supercritical are not dealt with by this code. Typical transients dealt with by this code are delayed supercritical ones such as those caused by electric power shutdown,  control rod ejections, cold water core inlet etc.

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4. METHOD OF SOLUTION

The time-step algorithm is based on a totally implicit scheme.
The neutron flux is approximated in space by a third degree polynomial expansion (not complete) in a CUBBOX-like way, but in this case the unknowns are not centered cell or interface fluxes, they are indeed average cell or interface ones (zero order moments).
The linear system is solved by an ADI iterative method well suited for the three dimensional case.
The nuclear data variation laws for a particular problem should be implemented in a subroutine called MATUPDATE which will be then compiled and linked with the code's main body.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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6. TYPICAL RUNNING TIME:

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS:

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9. STATUS

Package ID	Status date	Status
NEA-1506/01	22-MAR-2001	Masterfiled Arrived

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10. REFERENCES

- B. Montagnini,P. Soraperra,C. Trentavizi,M. Sumini,D.M. Zardini:
  A Well Balanced Coarse-Mesh Flux Expansion Method
  Annals of Nuclear Energy, Vol. 21, No. 1, pp. 45-43 (1994)
- B.Montagnini, M.Sumini, D.M.Zardini:
  A Coarse-mesh Method for Reactors Calculations:
  Proceedings of  IAEA Workshop on Nuclear Reactor Physics, Design
  and Safety, Trieste 1994. World Scientific Publishing co., New
  Jersey,1995

NEA-1506/01, included references:

- B. Montagnini, P. Raffaelli, M. Sumini and D.M. Zardini:
  A 3D Coarse-Mesh Time Dependent Code for Nuclear Reactor Kinetic
  Calculations
  Ann. Nucl. Energy Vol.23, No.6, pp.517-532, 1996
- G. Erbacci, R. Ansaloni, B. Montagnini, R. Scardovelli, M. Sumini
  and D. Zardini:
  Porting a Coarse-Mesh Neutron Diffusion Code on a Cray T3D
  Massively Parallel Computer
  (Reprint) HPCN Europe, Milano, 1995, Lecture Notes on Computer
  Science - 919
  B. Hertzberger, G. Serazzi, Eds., pp.318-328, Springer, Berlin,
  1995

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11. MACHINE REQUIREMENTS:

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-1506/01	FORTRAN-77

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

     B. Montagnini, P.Raffaelli, M. Sumini, D.M. Zardini
     Laboratorio di Ingegneria Nucleare Montecuccolino
     Univ. degli Studi di Bologna
     Via dei Colli, 16
     40136 BOLOGNA
     ITALY

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16. MATERIAL AVAILABLE

NEA-1506/01

source program   mag tapeDPOL3D.F Main program                      SRCTP
source program   mag tapeLANGE11.F Subrout. MATUPDATE, data updatingSRCTP
test-case data   mag tapeLANGE11.DAT Input file                     DATTP
test-case output mag tapeLANGE11.OUT Output file                    OUTTP
source program   mag tapeLANGE16.F Subrout. MATUPDATE, data updatingSRCTP
test-case data   mag tapeLANGE16.DAT Input file                     DATTP
test-case output mag tapeLANGE16.OUT Output file                    OUTTP
source program   mag tapeLANGE22.F Subrout. MATUPDATE, data updatingSRCTP
test-case data   mag tapeLANGE22.DAT Input file                     DATTP
test-case output mag tapeLANGE22.OUT Output file                    OUTTP
source program   mag tapeLANGERR.F Subrout. ERRIFT, data comparisonsSRCTP
miscellaneous    mag tapeMANENGL.DOC DPOL3D's input data (text file)MISTP
miscellaneous    mag tapeNEA.DOC DPOL3D's abstract                  MISTP
miscellaneous    mag tapeANNALS.DOC A 3D Coarse-Mesh Time Dep. Code MISTP
miscellaneous    mag tapeREPRINT.DOC Porting a Coarse-Mesh Neutron..MISTP
paper                    A 3D Coarse-Mesh Time Dependent Code (1995)PAPPT
paper                    Porting a Coarse-Mesh Neutron Diffus. Code PAPPT

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17. CATEGORIES

C. Static Design Studies
F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics

Keywords: diffusion, dynamics, reactor kinetics, time-dependent.