NEA-0187 SOREX-1.
SOREX-1, Worst Accident Simulation in Sora Pulsed Fast Reactor
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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| 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.
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.
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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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.
- 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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NEA-0187/01
| File name | File description | Records |
|---|---|---|
| NEA0187_01.001 | SOURCE & DATA 360/65 | 336 |
| NEA0187_01.002 | OUTPUT | 260 |
Keywords: accidents, finite difference method, pulsed reactors, radioactivity, reactor safety.