Computer Programs

IAEA1240 HEXAB-3D.

IAEA1240 HEXAB-3D.

HEXAB-3D, 3-D Few-Group Diffusion for Hexagonal Core Geometry

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: HEXAB-3D.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.

Program name	Package id	Status	Status date
HEXAB-3D	IAEA1240/01	Tested	14-MAR-2002

Machines used:

Package ID	Orig. computer	Test computer
IAEA1240/01	IBM 370 series	PC Pentium III,DEC ALPHA W.S.

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3. DESCRIPTION OF PROGRAM OR FUNCTION

A three-dimensional few-group calculational model based on diffusion theory has been developed for calculating the basic neutron physical characteristics of power reactors which have a hexagonal core configuration with a heterogeneous region structure in axial direction. There are two versions of the model:
- HEXAB-III-30  - the solution range in horizontal plane is 30 -
                  sector of reactor core
- HEXAB-III-360 - the solution range in horizontal plane is full                   core.

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4. METHOD OF SOLUTION

In the HEXAB-3D code the nine-point mesh-centered finite-difference approximation of neutron diffusion equation is applied. The standard inner-outer iterative strategy is used. Inner iterations are solved using two different incomplete factorization techniques: AGA two-sweep iterative method and modified AGA two-sweep iterative method both accelerated by the double successive overrelaxation procedure. The power method, combined with two- or three-term Chebishev polynomial acceleration for outer iterations is applied in the code. To improve the accuracy of the calculated integral and local reactor parameters without significantly increasing computer time and storage an effective approach has been developed. It decreases errors due to the use of coarse mesh by means of correcting the coefficients of finite- difference scheme.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum of 10 energy groups, 30 horizontal layers and 100 material compositions.

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6. TYPICAL RUNNING TIME

A Keff calculation for 3-D SNR-300 test problem in 360 degree - sector (full core) with 7940 space mesh points and 4 energy groups requires on the IBM 3031 under OS/VS1 approximately 4 minutes.

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7. UNUSUAL FEATURES OF THE PROGRAM:

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8. RELATED AND AUXILIARY PROGRAMS

FREIFE and FELDE: For dynamic allocation of the central computer storage.
DAFDEF: For data array input-output operations with direct access files.

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9. STATUS

Package ID	Status date	Status
IAEA1240/01	14-MAR-2002	Tested at NEADB

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10. REFERENCES

- K. Ivanov, M. Manolova and T. Apostolov:
  Application of Two-Sweep Iterative Method AGA DSOR in the Three-
  Dimensional Hexagonal Geometry Programme HEXAB-3D for Group
  Diffusion Calculations of fast Breeder Reactors
  Nuclear Energy 28, pp. 13-18, Sofia (1990).
- K. Ivanov, T. Apostolov and M. Manolova:
  HEXAB-3D Three-Dimensional Few-Group Coarse-Mesh Diffusion Code
  for Reactor Calculations
  Proc. of Internal Topical Meeting on Advances in Mathematics,
Computations and Reactor Physics, Pittsburg, USA, April 28 - May 2    (1991), V.5.

IAEA1240/01, included references:

- K. Ivanov, M. Manolova, T. Apostolov:
  IBM User's Guide to HEXAB-3D Code
  (Updated Version March 1991).
- K. Ivanov et al.:
  Verification of HEXAB-3D Code with FBR and WWER Benchmarks
- K.N. Ivanov et al.:
HEXAB-3D, A Three-Dimensional Few-Group Coarse-Mesh Diffusion Code
for Reactor Calculations
Proc. of Int. Topical Meeting on Advances in Mathematics, Computations
and Reactor Physics, Pittsburgh, USA April 28-May 2, 1991

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11. MACHINE REQUIREMENTS

Virtual storage required for the program is 1024K. IBM 3350 and/or IBM 3330 disk storage devices can be used for work files. The total disk space required is no larger than 40 cylinders on IBM 3350.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
IAEA1240/01	FORTRAN+ASSEMBLER

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: The program has been run under OS/VS1 and MVS.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHORS

          T.G. Apostolov, K.N. Ivanov, M.A. Manolova
          Institute for Nuclear Research and Nuclear Energy
          Bulgarian Academy of Sciences, Sofia, Bulgaria

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16. MATERIAL AVAILABLE

IAEA1240/01

test-case data   mag tapeHEXAB-3D Tape Description                  DATTP
test-case data   mag tapeHEXAB-3D JCL                               DATTP
source program   mag tapeHEXAB-3D Source Program (FORTRAN-G)        SRCTP
source program   mag tapeFELDE Subroutine Source Code (ASSEMBLER)   SRCTP
source program   mag tapeFREIFE Subroutine Source Code (ASSEMBLER)  SRCTP
source program   mag tapeDAFDEF Subroutine Source Code (ASSEMBLER)  SRCTP
test-case data   mag tapeInput Data Sample Problem                  DATTP
test-case output mag tapeHEXAB-3D Output Data Sample Problem        OUTTP
report                   IBM User's Guide (March 1991)              REPPT
report                   Verification of HEXAB-3D Code              REPPT

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17. CATEGORIES

C. Static Design Studies

Keywords: coarse mesh, few-group, hexagonal configuration, neutron diffusion equation.