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IssuesArchive of Issues2006-2pp.101-112

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V. A. Grigor'ev, "Application of probabilistic methods of fracture mechanics to the risk analysis of violation of safety criteria for a reactor facility," Mech. Solids. 41 (2), 101-112 (2006)
Year 2006 Volume 41 Number 2 Pages 101-112
Title Application of probabilistic methods of fracture mechanics to the risk analysis of violation of safety criteria for a reactor facility
Author(s) V. A. Grigor'ev (Moscow)
Abstract In the world practice of justification of strength, reliability, and safety of power units, the techniques associated with the determination of the risk of violation of the safety criteria for these units have been developed. In Russia, the concept of risk has been involved in the Law of the Russian Federation "On Technical Regulation". In the present paper, the risk of the violation of the safety criteria for a reactor facility is defined as the product of the probability of the failure or the critical state (initiation event) of the reactor facility equipment by the conditional probability of the violation of the safety criteria (consequences), provided that the initiation event has occurred.

The creation and application of methods associated with the concept of risk for the power unit operation safety analysis leads to the classification of the reactor facility equipment according to the probability of the influence of the initiation events on the safety of this facility, i.e., the equipment should be classified according to a measure of the risk of the safety violation. In this connection one can consider the influence of failures and the critical state of the equipment on the violations of the safety criteria threatening with the destruction of the reactor's body, major damage of the core region, radioactivity release beyond the containment shell, and the radioactive contamination of the environment.

In the methodology based on the concept of risk, especially important are the problems related to the development of defects in the metal of the equipment and pipelines. The current paper presents the basic principles of the application of the probabilistic methods of fracture mechanics for the reliability analysis of the equipment and the evaluation of the risk of the safety criterion violation for the reactor facility. These principles are developed for the analysis of the probability of failure of the reactor's body and heat exchanger pipes in a steam generator.
References
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3.  A. A. Tutnov and V. V. Grachev, "Calculation of the probability for the beginning of brittle fracture of pressure vessels," Atomnaya Energiya, Vol. 64, No. 3, pp. 188-194, 1988.
4.  V. A. Grigor'ev, "A concept for the application of the probabilistic methods of fracture mechanics for the reliability analysis of the equipment and pipelines of reactor facilities with water-cooled water-moderated energy reactors," in Second All-Russia Science-and-Technology Conference "Providing Safety for Nuclear Power Plants with Water-cooled Water-moderated Energy Reactors" [in Russian], Podolsk, Moscow Region, 2001; Transactions of the Experimental Design Office "Gidropress", Vol. 1, pp. 132-147, 2001.
5.  V. A. Grigor'ev, "Probabilistic analysis of fracture of elements of a reactor facility," in N. V. Sharyi, V. P. Semishkin, V. A. Pimenov, and Yu. G. Dragunov, Strength of Basic Equipment and Pipelines of WWER [in Russian], Chapter 8, pp. 320-407, IKTs "Akademkniga", Moscow, 2004.
6.  V. A. Grigor'ev, "Combined fracture model for the reliability analysis of the equipment of reactor facilities with WWER," in Issues of Nuclear Science and Technology. Ser. Providing Safety for Nuclear Power Plants. Issue 7. Reactor facilities with WWER [in Russian], pp. 49-60, Podolsk, 2004.
7.  V. P. Gorbatykh, "The influence of the combination of ammonia and copper-bearing alloys on the corrosion cracking of matrices of steam generators from austenitic steels," in Materials of the IAEA Regional Seminar, Udomlya, 2000 [in Russian], pp. 123-130, ENITs VNIIAES, Moscow, 2001.
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10.  B. V. Gnedenko, Yu. K. Belyaev, and A. D. Solov'ev, Mahematical Methods in Reliability Theory [in Russian], Nauka, Moscow, 1965.
11.  V. A. Grigor'ev, "The value of the reliability criterion as applied for the prediction of service life for reactor facilities," in Proceedings of the 7th Intrnat. Conference "Material Engineering Aspects in Designing, Manufacturing, and Operating Nuclear Power Plant Equipment," pp. 150-162, St. Petersburg, 2002.
12.  General Privisions for Accident Prevention in Nuclear Power Plants (OPB-88/97), PNAE G-01-011-97 [in Russian], Atomizdat, Moscow, 1997.
13.  V. A. Grigor'ev, "The development of an approach to detrmining the fracture probability for the body of reactor WWER-440," in Issues of Nuclear Science and Technology. Ser. Accident Prevention in Nuclear Power Plants. Issue 1. Reactor Facilities with WWER [in Russian], pp. 10-25, Podolsk, 2002.
14.  K. Wallin, "The scatter in K1C result," Engineering Fracture Mechanics, Vol. 19, No. 6, pp. 1085-1093, 1984.
15.  Technique for the Operational Determination of the Service Life for the Bodies of WWER Nuclear Reactors (MRK-SKhR-2000). RD EO 0353-02 [in Russian], Rosenergoatom, St. Petersburg, Moscow, 2000.
16.  S. E. Davidenko, N. B. Trunov, V. A. Grigor'ev, and V. V. Denisov, "Improvement of inspection and repair of heat exchange pipes of steam generators for nuclear power plants with WWER," in Issues of Nuclear Science and Technology. Ser. Accident Prevention in Nuclear Power Plants. Issue 9. Reactor Facilities with WWER [in Russian], pp. 55-63, Podolsk, 2005.
17.  V. A. Grigor'ev, "A method for the operational integrity analysis of heat exchange pipes for PGV-type steam generators", in Issues of Nuclear Science and Technology. Ser. Accident Prevention in Nuclear Power Plants. Issue 5. Reactor Facilities with WWER [in Russian], pp. 45-57, Podolsk, 2004.
Received 25 November 2005
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