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Present state of the problem of managing the service life of steam generators used at nuclear power stations equipped with VVER reactors

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Abstract

Modern state of steam generators used at nuclear power stations equipped with VVER reactors, existing problems, and topical matters of managing their service life are considered.

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References

  1. V. A. Grigor’ev, V. V. Ulanov, A. A. Shubin, et al., “Substantiating the Requirements for Trustworthiness of Examining Heat-Transfer Tubes of PVG Steam Generators Using the Eddy-Current Method,” Vopr. Atomn. Nauki, Tekhn., Ser. Obesp. Bezopasn. AES, No. 13 (2006).

  2. N. B. Trunov, S. E. Davidenko, V. S. Popadchuk, and R. Ju. Zhukov, “Actual Problems of VVER SG Tubing Service Life Management. ICONE17-75096,” in Proceedings of the 17th International Conference on Nuclear Engineering ICONE 17, Brussels, Belgium, July 12–16, 2009.

  3. RD EO (Guiding Document) 0330-01. A Guide on Strength Calculations of Equipment and Pipelines of RBMK and VVER Reactor Installation at the State of Their Operation (OAO Rosenergoatom Concern, Moscow, 2004) [in Russian].

  4. Strategy for Assessment of WWER Steam Generator Tube Integrity. IAEA-TECDOC-1577 (IAEA, Vienna, 2007).

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Original Russian Text © N.B. Trunov, S.E. Davidenko, V.S. Popadchuk, N.N. Davidenko, A.A. Berezanin, D.F. Gutsev, V.N. Lovchev, D.A. Usanov, 2011, published in Teploenergetika.

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Trunov, N.B., Davidenko, S.E., Popadchuk, V.S. et al. Present state of the problem of managing the service life of steam generators used at nuclear power stations equipped with VVER reactors. Therm. Eng. 58, 184–189 (2011). https://doi.org/10.1134/S0040601511030141

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  • DOI: https://doi.org/10.1134/S0040601511030141

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