DYNAMIC AVAILABILITY ASSESSMENT ON TEHRAN RESEARCH REACTOR WATER COOLING SYSTEM

Publish Year: 1392
نوع سند: مقاله کنفرانسی
زبان: English
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شناسه ملی سند علمی:

NCMII01_455

تاریخ نمایه سازی: 22 اردیبهشت 1393

Abstract:

Failures in important safety equipment of nuclear reactors can result in grave deterioration of defense-in-depth barriers of safety. Thus, using an efficient and proactive approach in reliability and safety analysis of nuclear reactors is of utmost importance. Dynamic reliability methods are powerful mathematical frameworks capable of handling interactions among components and process variables explicitly. In principle, they constitute a more realistic modelling of systems for the purpose of reliability analysis. In this paper, ageing effects on availability are evaluated using dynamic analysis by considering impact of maintenance policy and scheduled tasks on Tehran research reactor (TRR) cooling water system, with the help of dynamic fault tree analysis (DFTA), the estimation results for 40 years ageing of the reactor are presented. Keeping maintenance variables constant and in view of decreasing reliability it is noted that availability of the cooling water system decreases with time.

Keywords:

Ageing , , Availability , Cooling water system of Tehran research reactor , Dynamic reliability , Dynamic fault tree analysis

Authors

sajjad bahrebar

Science and Research Branch Islamic Azad University of Tehran

sima rastayesh

Science and Research Branch Islamic Azad University of Tehran

kamran sepanloo

Daneshestan Institute of Higher Education of Saveh

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  • (1966): Safety Analysis Report for Tehran Research Reactor, American Machine ...
  • (1988): T.R.R. Amendment o the Safety Report, Argentina, Prepared by ...
  • IAEA -TECDOC-4? 8 , (1988): Component Reliability Data for _ ...
  • IAEA-TECD OC-590, (1991): Determining Safety Importance of Systems and Components ...
  • IAEA -TECDOC- 5 17, (1989): Application of Probabilistic safety assessment ...
  • IAEA -TECDOC- 930. , (1997): Generic component reliability data for ...
  • IAEA-TECHD OC-63 6, (1992): Manual on reliability data collection for ...
  • IAEA -TECHDOC 643 , (1992): Research reactor core conversion guidebook, ...
  • (1 997) :Electronics and Sensing Component and Reliability Data for ...
  • O Connor, A. N. (2011): Probability Distributions Used in Reliability ...
  • IAEA _ TECDOC-4) _ (1986): Probabilistic Safety Assessment for Research ...
  • Modarres, M., (2006): What Every Engineer Should Know about Reliability ...
  • Modarres, M., Risk Analysis in Engineering, Taylor & Francis. ...
  • Ghofrani, M.B., Damghani, S.A., (2002): Determination of the safety importance ...
  • NUREG/CR 28 15.. (1984): Probabilistic Safety Analysis Procedures Guide, Prepared ...
  • Aneziris, O. N. Housiadas, I.A. C.: Probabilistic Safety Analysis of ...
  • Cepin, M. Mavko. B., (2001): A dynamic fault tree, Reactor ...
  • Distefano, S. Dipt., Xing, L (2006): A new approach to ...
  • Distefano, S. Dipt., Puliafito, A. (2007): Dynamic Reliability Block Diagrams ...
  • Labeaua, P.E. Smidtsb, C. S waminathanb, S. (2000): Dynamic reliability: ...
  • Robidoux, R. Xu, H. Xing, L. Zhou, M. C.: Automated ...
  • Manian, R. Bechta, J. Coppit, D. D. Sullivan, K. J.: ...
  • Chiacchio1, F. Compagno, L. D Urso, D. Manno1, G. Trapani, ...
  • Rausand M., Hoyland, A. (2003): System Reliability Theory: Models, Statistical ...
  • Manian, R. Dugan, J. Coppit, D, Sullivan, K.: Combining various ...
  • نمایش کامل مراجع