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.
Similar content being viewed by others
References
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).
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.
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].
Strategy for Assessment of WWER Steam Generator Tube Integrity. IAEA-TECDOC-1577 (IAEA, Vienna, 2007).
Author information
Authors and Affiliations
Additional information
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.
Rights and permissions
About this article
Cite this article
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
Published:
Issue Date:
DOI: https://doi.org/10.1134/S0040601511030141