Improving reactor safety systems using component redundancy allocation technique

• Autorzy: Habib A. , Ashry H. , Shokr A. , Dakhly A.
• Języki publikacji: EN

Abstrakty

EN

This paper addresses the improvements to the reliability of the safety systems of nuclear reactors using redundancy allocation technique. The study has been carried out using the Probabilistic Safety Assessment (PSA). PSA involves, among others, the use of fault and event tree tools in the evaluation of the safety system failure probabilities and the quantification of annual occurrence probability of the accidental conditions postulated in the design of the nuclear reactors. The PSA has been presented and discussed. The Egypt Second Research Reactor, ETRR-2, has been used as a case study. The failure probability of the already existing safety systems has been reviewed. The effect of the allocation of more redundant components to the existing safety systems on the failure probability of the systems has been evaluated. The event trees for two selected initiating events, from those events postulated in the ETRR-2 design, have been studied considering the allocation of more redundant components to the safety systems. The result of the study showed that further improvement could be introduced to the reliability of the Confinement Ventilation System (CVS).

Słowa kluczowe

EN

redundancy allocation; risk management; safety systems; probabilistic safety assessment; ETRR-2

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2005
• Tom: Vol. 50, nr 3
• Strony: 105--112
• Opis fizyczny: Bibliogr. 10 poz., rys.

Twórcy

autor

Habib A.

• Department of Mathematics, Faculty of Science, El-Minufiya University, Shibeen El-koom, El-Minufiya, Egypt

autor

Ashry H.

• National Center for Radiation Research and Technology, Atomic Energy Authority, Cairo, Egypt, Tel.: [phone], Fax: [phone]

autor

Shokr A.

• Atomic Energy Authority, ETRR-2, 13759, Abou zabal, Egypt

autor

Dakhly A.

• National Center for Radiation Research and Technology, Atomic Energy Authority, Cairo, Egypt, Tel.: [phone], Fax: [phone]

Bibliografia

• 1. Abdelrazek ID (2002) The development of the MPR project. In: Proc of the 5th Arab Conf in the Peaceful Uses of Atomic Energy, November 2000, Lebanon, I:41−66.
• 2. Elsayed AE (1996) Reliability engineering. Addison Wesley Longman, USA.
• 3. IAEA (1987) Probabilistic safety assessment for research reactors. IAEA-TECDOC-400. IAEA, Vienna.
• 4. IAEA (1989) Applications of probabilistic safety assess-ment to research reactors. IAEA-TECDOC-517. IAEA, Vienna.
• 5. IAEA (1992) Application of the single failure criteria. IAEA Safety Series 50-P-1. IAEA, Vienna.
• 6. IAEA (1994) Safety assessment of research reactors and preparation of the safety analysis report. Safety Series 35-G-1. IAEA, Vienna.
• 7. INVAP-AEA (1995) CWIS descriptive technical report. ETRR-2 Document #0767-0240-2VAPE-003-1B.
• 8. INVAP-AEA (1995) Second shutdown system descriptive technical report. ETRR-2 Document #0767-0850-2VAPE-003-1A.
• 9. INVAP-AEA (1996) Reactor hall ventilation system: Technical report. ETRR-2 Document #0767-3410- 2VAPQ-001-1O.
• 10. INVAP-AEA (1999) Final safety analysis report of ETRR-2. Document #0767-5325-3IBLI-001-1A.