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NEA-0187 SOREX-1.

SOREX-1, Worst Accident Simulation in Sora Pulsed Fast Reactor

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1. NAME OR DESIGNATION OF PROGRAM:  SOREX-1.
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2. COMPUTERS
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Program name Package id Status Status date
SOREX-1 NEA-0187/01 Tested 01-MAR-1968

Machines used:

Package ID Orig. computer Test computer
NEA-0187/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The programme simulates a major accident in a pulsed fast reactor of the SORA type. The main accident considered is that caused by the sudden breakage of the pulsation device during operation. The programmme solves the equations of motion of the broken fragment in collision with the core and evaluates the resulting reactivity input. Using this reactivity, the programme simultaneously solves the equations of a modified Bethe-Tait model to obtain the explosive nuclear energy release. SOREX-1 is also adapted to simulate milder accidents caused by abnormal reactivity drifts of fuel melting during otherwise normal (pulsed or steady) operation.
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4. METHOD OF SOLUTION

All differential equations are expressed in approximate finite difference form and solved step by step over a chain of time points. The spacing of this chain is reduced as the nuclear excursion accelerates and the accuracy of the finite difference representation is thereby kept roughly constant.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The programme does not properly treat very mild accidents for which the Bethe-Tait model is inappropriate.
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6. TYPICAL RUNNING TIME

Depends strongly on the particular excursion studied, but always of the order of a few seconds per case.
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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-0187/01 01-MAR-1968 Tested at NEADB
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10. REFERENCES

- J. Randles:
  Theoretical Analysis of Hypothetical Destructive Accidents in a Pulsed Fast Reactor paper SM-101/46, Symposium on Fast Reactor Physics and Related Safety Problems, Karlsruhe (1967).
- J. Randles:
  Analysis of Accidents in Pulsed Fast Reactors - The Programme DOPPELAS and SOREX-1 EURATOM. Report to be published.
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11. MACHINE REQUIREMENTS

26k bytes in the 360/65 version and 6k locations in 7090 version.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0187/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBSYS for the 7090 and HASP for the 360/65 version.
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  The 360/65 version is in double precision.
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15. NAME AND ESTABLISHMENT OF AUTHOR

            J. Randles
            Commission des Communautes Europeennes
            Etablissement Ispra
            Reactor Physics Dept.
            21020 - Ispra (Varese)
            Italy
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16. MATERIAL AVAILABLE
NEA-0187/01
File name File description Records
NEA0187_01.001 SOURCE & DATA 360/65 336
NEA0187_01.002 OUTPUT 260
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, finite difference method, pulsed reactors, radioactivity, reactor safety.