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NEA-1006 ASDIC.

ASDIC, Fast Reactor Hexagonal 3 Component Fuel Pin Diffusion Coefficient

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1. NAME OR DESIGNATION OF PROGRAM:  ASDIC.
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2. COMPUTERS
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Machines used:

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3. DESCRIPTION OF PROGRAM OR FUNCTION

ASDIC calculates radial and axial diffusion coefficients in a fast reactor hexagonal fuel assembly composed of three media, fuel pins, coolant (which may be voided) and hexagonal outer tube. The zero buckling approximation is assumed.
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4. METHOD OF SOLUTION

The program performs a numerical calculation of an analytical formula involving special functions and integrals.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Bidimensional
coolant gaps must exist.
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6. TYPICAL RUNNING TIME

The running time is typically less than 1 CPU second (CDC7600).
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

MOBIDIC calculates radial and axial diffusion coefficients in a fast reactor INFINITE lattice, with a non-zero buckling.
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9. STATUS

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10. REFERENCES:
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11. MACHINE REQUIREMENTS

To run the test case on CDC CYBER 740, 63,300 (octal) words of main storatge are required.
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12. PROGRAMMING LANGUAGE(S) USED

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

SCOPE-2.
The test case was executed on CDC CYBER 740 under NOS 1.4-531.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         P. Benoist and T. Duracz
         C.E.N Saclay
         France
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16. MATERIAL AVAILABLE
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17. CATEGORIES

Keywords: cell calculation, fast reactors, neutron transport theory.