Abstract
A two-stage approach to evaluating the probability of leak appearing in the flange joint as a result of a failure of the securing studs is described. First the probability of only one stud failing is calculated. This probability depends on, specifically, the integrity of all other studs. The probabilities of different combinations of the relative arrangements of whole and failed studs are calculated at the second stage. The method is illustrated for the calculation of the probability of a leak in the region of the collector cover for a PGV-1000 steam generator. Normative data on the strength and mechanical characteristics of the structural materials and loads corresponding to the nominal operating regimes are used in the calculations.
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References
B. A. Sevast’yanov, A Course on the Theory of Probability and Mathematical Statistics, Nauka, Moscow (1982).
B. I. Lukasevich, N. B. Trunov, Yu. G. Dragunov, and S. E. Davidenko, Steam Generators of WER Reactor Facilities for Nuclear Power Plants, ITsK “Akademkniga,” Moscow (2004).
Aleksei S. Kiselev, Aleksandr S. Kiselev, A. A. Tutnov, and O. I. Ivanova, “Salient features of a model of and the results of investigations of the stress-strain state of the elements of the flange joint of the collector cover of a PGV-1000 steam generator,” in: Methods and Software for Performing Strength Calculations, NIKIÉT, Moscow (2002), pp. 259–268.
“Annotation of the MAVR1.1 computer code,” Vopr. At. Nauk. Tekhn., Ser. Fiz. Yad. Reakt., No. 3, 70–73 (1995).
D. M. Shur, E. Yu. Rivkin, G. N. Merinov, and R. V. Belikova, “Statistical crack resistance of 38KhN3MFA steel used for the securing parts of the main flange joint of a VVÉR-1000 reactor vessel,” in: Crack Resistance of Materials and Structural Components of a Nuclear Reactor System, Énergoatomizdat, Moscow (1990), pp. 65–73.
Standards for Calculating the Strength of Equipment and Pipelines of Nuclear Power Facilities PNAÉ G-7-002-86, Énergoatomizdat, Moscow (1986).
V. A. Grigor’ev, A. A. Stobetskii, V. N. Siryapin, et al., “Approach to evaluating the probability of leaks in equipment connections in WER reactor facilities,” Vopr. At. Nauk. Tekhn., Ser. Obespech. Bezop. AÉS, No. 3. Reakt. Ustan. WER (2003), pp. 3–13.
A. A. Stobetskii, V. A. Grigor’ev, and V. V. Ulanov, “Evaluating the probability of detachment of the collector cover of a PGV-1000 steam generator using probabilistic methods of failure mechanics,” in: 7th International Seminar on Horizontal Steam Generators, Podol’sk (2006), pp. 143–152.
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Translated from Atomnaya Énergiya, Vol. 102, No. 6, pp. 344–347, June, 2007.
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Tutnov, A.A., Loskutov, O.D. Evaluation of the probability of a leak in the flange joint of a steam-generator collector cover as a result of stud failure. At Energy 102, 426–429 (2007). https://doi.org/10.1007/s10512-007-0067-2
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DOI: https://doi.org/10.1007/s10512-007-0067-2