Computer Programs

NEA-0176 HETERO.

NEA-0176 HETERO.

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

NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, AUXILIARIES, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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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.