Computer Programs
NEA-0176 HETERO.
last modified: 01-JUN-1967 | catalog | categories | new | search |

NEA-0176 HETERO.

HETERO, Flux and Power Distribution in Thermal Reactor by 3-D, 2 Group Line Source Sink Method

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1. NAME OR DESIGNATION OF PROGRAM:  HETERO.
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2. COMPUTERS
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Program name Package id Status Status date
HETERO NEA-0176/01 Tested 01-JUN-1967

Machines used:

Package ID Orig. computer Test computer
NEA-0176/01 IBM 7090 IBM 7090
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The line source-sink method is used to calculate the flux and power distribution in a thermal reactor. 3 dimensions and 2 energy groups are used. Possibilities for burnup calculations and fuel movements are incorporated.
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4. METHOD OF SOLUTION

The eigenvalue (the reactivity) and the eigenvector are solved by direct iteration.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maximum number of element groups (n) - 150
maximum number of Fourier components (m) - min (64, 1500/n).
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6. TYPICAL RUNNING TIME:  Depends strongly on the problem type.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0176/01 01-JUN-1967 Tested at NEADB
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10. REFERENCES

- A. Jonsson, G. Naeslund:
  Description of Heterogeneous Programmes for Macroscopic Reactor Calculations
  Part V.3. HETERO. Internal report RFN-226/RFR-603.
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11. MACHINE REQUIREMENTS:  32k store, 9 tape units.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0176/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBJOB.
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  Easily converted to IBM 7090 and GE 625.
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15. NAME AND ESTABLISHMENT OF AUTHOR

G. Naeslund
                                   AB Atomenergi
                                   Box 43041
                                   Stockholm 43
                                   Sweden
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16. MATERIAL AVAILABLE
NEA-0176/01
File name File description Records
NEA0176_01.001 SOURCE & DATA F4 V13 2675
NEA0176_01.002 OUTPUT 441
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, eigenvalues, eigenvectors, fuel elements, iterative methods, neutron flux, power distribution, thermal reactors, three-dimensional, two-group.