Computer Programs
IAEA1173 NEHEX-3D.
last modified: 31-JAN-1995 | catalog | categories | new | search |

IAEA1173 NEHEX-3D.

NEHEX-3D, 3-D Neutron Diffusion for Fast Reactors and WWER in Hexagonal Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  NEHEX-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
NEHEX-3D IAEA1173/01 Tested 31-JAN-1995

Machines used:

Package ID Orig. computer Test computer
IAEA1173/01 ES-1040 DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Neutronics calculation of fast  and WWER type reactors with hexagonal assemblies (determination of keff value, group neutron fluxes and thermal power).
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4. METHOD OF SOLUTION

The method is based on the following ideas:
- nodal approach
- transverse integration technique
- expansion of one-dimensional neutron flux inside the node in   polynomials up to the third order
- formulation of nodal equations in the form of response matrix   equation
- solution of resulting nodal algebraic equations by means of   iterative method
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Geometry: 30 deg. reflectional and 60 deg. rotational symmetry;
Maximum number of subassemblies :       NN = 100
Maximum number of energy groups :       NG =   4
Maximum number of axial layers  :       NZ =  20
Maximum number of different materials : NM = 50
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6. TYPICAL RUNNING TIME:
IAEA1173/01
The test case included in this package was executed by  the NEA-DB on a DEC/VAX 6000-510 computer in 13 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:  Assumption of homogeneous nodes.
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8. RELATED AND AUXILIARY PROGRAMS

No auxiliary program is necessary.  NEHEX-3D is an extension of the two-dimensional program NEHEX1.
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9. STATUS
Package ID Status date Status
IAEA1173/01 31-JAN-1995 Tested at NEADB
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10. REFERENCES

- B. Kujal
An Effective Method of Solving the Multigroup Diffusion Problem in    Hexagonal Geometry,
  UJV 7839-R (1987).
- B. Kujal
  The Method of the Three-Domensional Multigroup Diffusion Program
  in Hexagonal Geometry (in Czech),
  UJV 8222-R (1988).
IAEA1173/01, included references:
- B. Kujal:
  NEHEX-3D - A Multigroup Diffusion Nodal Computer Code for Three
  Dimensional Hexagonal Geometry. Code Description and Validation
  NRI 8384-R,T (1987).
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11. MACHINE REQUIREMENTS

- 1300kB of high speed memory (for calculation)
- printer
- card reader or discs (only for input data)
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1173/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/360 FORTRAN H
LEVEL 21.8.
IAEA1173/01
The program was installed by NEA-DB under VAX VMS 5.5-2. The source program was compiled on the VAX FORTRAN compiler Version 5.5-98.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  Code
should be compatible with IBM 370.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          B. Kujal
          Nuclear Research Institute
          250 68 Rez, Czechoslovakia
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16. MATERIAL AVAILABLE
IAEA1173/01
File name File description Records
IAEA1173_01.001 Information file 72
IAEA1173_01.002 NEHEX3D Fortran source 1221
IAEA1173_01.003 Test input data 87
IAEA1173_01.004 Test output data with IBM 1345
IAEA1173_01.005 Test output data with VAX 1349
IAEA1173_01.006 JCL cards for IBM 11
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17. CATEGORIES
  • C. Static Design Studies

Keywords: criticality, fast reactors, hexagonal lattices, neutron diffusion equation, neutron flux, three-dimensional.