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Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel campaign

https://doi.org/10.26583/gns-2024-02-06

EDN: KKDMXX

Abstract

The welded joint zone (WJ) No. 111 is a welding unit for the "hot" collector of the primary coolant to the DN1200 steam generator nozzle. The experience of operation of steam generators PGV-1000M of NPP power units with VVER-1000 shows that the WJ zone No. 111 is prone to the formation and development of operational defects. According to the results of periodic non-destructive testing of the WJ No. 111 zone performed at the PG of various power units of the VVER-1000 NPP, cases of detection of extended planar-type discontinuities, including through ones, were repeatedly recorded. Thus, this zone is one of the most critical zones of the reactor plant (RU) with VVER -1000. The root cause of the formation and development of operational defects has not yet been identified. Solving the problem of cracking of WJ No. 111 steam generators of nuclear power plants with VVER-1000 is one of the priority areas for improving the safety of operation of the power unit during the over-design service life. This problem is determined by a complex combination of temperature conditions, mechanical and corrosive effects, is relevant and has not yet been definitively solved. Therefore, it is very important to ensure the collection of reliable data on the actual stress-strain state of the WJ No. 111 zone in various operating modes (pressure loading of steam generators, heating/cooling of the power unit, hydraulic testing of the 1st and 2nd circuits). The article reveals the approaches and stages of creating and applying a strain gauge installation to ensure metrological suitability in the conditions of a campaign fuel company at an NPP power unit by using an adequate physical model to obtain additive and multiplicative correction coefficients.

About the Authors

Yu. V. Krasnikov
VASO ENGINEERING BUREAU LLC
Russian Federation

Can. Sci. (Engin.), Head, Chief Designer



V. P. Povarov
Branch of JSC Concern Rosenergoatom Novovoronezh Nuclear Power Plant (Novovoronezh NPP)
Russian Federation

Dr. Sci. (Engin.), Head



A. M. Stepanov
VASO ENGINEERING BUREAU LLC
Russian Federation

Head of the Scientific Research Department



S. G. Fish
LLC «RESOURCE»
Russian Federation

Can. Sci. (Engin.), Deputy Director for Development



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Review

For citations:


Krasnikov Yu.V., Povarov V.P., Stepanov A.M., Fish S.G. Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel campaign. Nuclear Safety. 2024;14(2):61-72. (In Russ.) https://doi.org/10.26583/gns-2024-02-06. EDN: KKDMXX

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ISSN 2305-414X (Print)
ISSN 2499-9733 (Online)