Analysis of eddy-current testing and metallographic examinations for corrosion damages of heat exchanging tubes in NPP steam generators

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dc.citation.epage15
dc.citation.issue1
dc.citation.spage7
dc.contributor.affiliationНаціональний університет “Львівська політехніка”
dc.contributor.affiliationLviv Polytechnic National University
dc.contributor.authorКоваленко, Тетяна
dc.contributor.authorЛис, Степан
dc.contributor.authorВострес, Володимир
dc.contributor.authorKovalenko, Tetiana
dc.contributor.authorLys, Stepan
dc.contributor.authorVostres, Volodymyr
dc.coverage.placenameЛьвів
dc.coverage.placenameLviv
dc.date.accessioned2023-09-14T07:56:04Z
dc.date.available2023-09-14T07:56:04Z
dc.date.created2021-06-01
dc.date.issued2021-06-01
dc.description.abstractРозглянуто механізми корозійних пошкоджень теплообмінних труб (ТОТ) парогенератора ПГВ-1000 у різних режимах його роботи. Встановлено, що корозійні дефекти локалізуються переважно в нижній частині трубних пучків парогенератора. Проведено дослідження корозійних пошкоджень теплообмінних труб парогенератора ПГВ-1000. Виконано порівняльний аналіз результатів вихорострумового контролю (ВСК) ТОТ парогенератора отриманих за допомогою двох різних систем ВСК “TEDDY-8”, “MIZ-30” та зіставлення цих даних із результатами металографічних досліджень дефектів. Встановлено, що відсоток ураження металу за результатами металографії для абсолютної більшості проаналізованих дефектів перевищує дані ВСК. В основному різниця становить 10–15 %, в окремих випадках – до 25 %. Доведено, що тонкостінні ТОТ парогенератора не повинні мати значних або наскрізних дефектів з метою забезпечення надійної роботи ТОТ ПГВ-1000, що є однією з найважливіших задач на АЕС.
dc.description.abstractThis paper represents the mechanism for corrosion damages of heat exchanging tubes (HET) of a steam generator PGV-1000 for various operational conditions. It was determined that corrosion damages locate mainly at the bottom of the steam generator bundled tubes. An investigation into the corrosion damages of HET was conducted in terms of PGV-1000 steam generator. The results of eddy-current testing (ECT) for steam generator HET performed by two different ECT systems “TEDDY-8”, “MIZ-30” were analyzed and compared to the results of metallographic examination of defects. It was determined that the percentage of rusted metal according to the metallography data in the absolute majority of analyzed defects surpassed the ECT ones. The difference is equal to 10–15 % in most cases and up to 25 % in some cases. It was proved that the thin-walled HET should not have significant or penetrating defects for ensuring the reliable operation of PGV-1000 HET, which is the most important task to do at a nuclear power plant (NPP).
dc.format.extent7-15
dc.format.pages9
dc.identifier.citationKovalenko T. Analysis of eddy-current testing and metallographic examinations for corrosion damages of heat exchanging tubes in NPP steam generators / Tetiana Kovalenko, Stepan Lys, Volodymyr Vostres // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2020. — Vol 6. — No 1. — P. 7–15.
dc.identifier.citationenKovalenko T. Analysis of eddy-current testing and metallographic examinations for corrosion damages of heat exchanging tubes in NPP steam generators / Tetiana Kovalenko, Stepan Lys, Volodymyr Vostres // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2020. — Vol 6. — No 1. — P. 7–15.
dc.identifier.urihttps://ena.lpnu.ua/handle/ntb/59995
dc.language.isoen
dc.publisherВидавництво Львівської політехніки
dc.publisherLviv Politechnic Publishing House
dc.relation.ispartofEnergy Engineering and Control Systems, 1 (6), 2020
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dc.relation.references[2] S. I. Brykov, H. F. Banyuk, N. B. Trunov, Y. V. Kharytonov, S. N. Susakin, N. N. Davydenko. Role of water-chemical regime of second contour in resource management for steam generators of NPP with WWER // WANO and IAEA Workshop “Optimisation of steam generators operating regimes for NPP power units”, Rivne NPP, Ukraine, June 11–14, 2002. (in Russian)
dc.relation.references[3] “Report on the condition of steam generators PGV-440 and PGV-1000 of power units of Ukrainian NPPs for 2012”, approved on 09.07.2013. (in Russian)
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dc.relation.references[5] V. N. Voevodyn, A. S. Mytrofanov, S. V. Hozhenko, R. L. Vasylenko, I. N. Shapoval, E. A. Kraynyuk, A. V. Bazhukov, A. N. Paliy, P. E. Melnyk. Analysis of data on monitoring the heat exchanging pipes of PGV-1000 steam generators at the South-Ukraine NPP // Issues of nuclear science and technology, 2018, No. 5 (117), p. 82–86. http://dspace.nbuv.gov.ua/handle/123456789/147705. (in Russian)
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dc.relation.referencesen[1] N. B. Trunov, S. A. Lohvinov, Y. H. Drahunov. Hydrodynamic and thermo-chemical processes in steam generators of NPP with WWER. M., Energoatomizdat, 2001, 316. (in Russian)
dc.relation.referencesen[2] S. I. Brykov, H. F. Banyuk, N. B. Trunov, Y. V. Kharytonov, S. N. Susakin, N. N. Davydenko. Role of water-chemical regime of second contour in resource management for steam generators of NPP with WWER, WANO and IAEA Workshop "Optimisation of steam generators operating regimes for NPP power units", Rivne NPP, Ukraine, June 11–14, 2002. (in Russian)
dc.relation.referencesen[3] "Report on the condition of steam generators PGV-440 and PGV-1000 of power units of Ukrainian NPPs for 2012", approved on 09.07.2013. (in Russian)
dc.relation.referencesen[4] I. M. Neklyudov, V. M. Azhazha, A. S. Mytrofanov, L. S. Ozhyhov, E. A. Kraynyuk, V. H. Lesnaya, P. A. Mishchenko. Atlas of operational defects in the heat transfer tubes of steam generators of nuclear power plants with WWER-type reactors: Directory-catalog. Intellectual property of National Science Center, Kharkiv Institute of Physics and Technology, Certificate No. 20514, Kharkiv, 2012, p. 237. (in Russian)
dc.relation.referencesen[5] V. N. Voevodyn, A. S. Mytrofanov, S. V. Hozhenko, R. L. Vasylenko, I. N. Shapoval, E. A. Kraynyuk, A. V. Bazhukov, A. N. Paliy, P. E. Melnyk. Analysis of data on monitoring the heat exchanging pipes of PGV-1000 steam generators at the South-Ukraine NPP, Issues of nuclear science and technology, 2018, No. 5 (117), p. 82–86. http://dspace.nbuv.gov.ua/handle/123456789/147705. (in Russian)
dc.relation.referencesen[6] J. Degmová, J. Dekan, V. Slugeň, C. Thees, I. Smieško, P. Šeliga. Analysis of steam generators corrosion products from slovak NPP Bohunice, International Journal of Corrosion, 2012, Volume 2012, 1–6. https://doi.org/10.1155/2012/643727
dc.relation.referencesen[7] G. Shimov, A. Serebryakov, A. Serebryakov. Experimental study of the method for resistance heat treatment of tubes for steam generator, Key Engineering Materials, 2017, Vol. 74, 141–147. https://doi.org/10.4028/www.scientific.net/KEM.746.141
dc.relation.referencesen[8] PN-D.0.03.539-14. Action plan to improve the reliability of steam generators and condensers of NPP turbine units of National Nuclear Energy Generating Company "Energoatom" for the period 2014–2020, p. 27. (in Russian)
dc.relation.urihttp://dspace.nbuv.gov.ua/handle/123456789/147705
dc.relation.urihttps://doi.org/10.1155/2012/643727
dc.relation.urihttps://doi.org/10.4028/www.scientific.net/KEM.746.141
dc.rights.holder© Національний університет “Львівська політехніка”, 2020
dc.subjectпарогенератор
dc.subjectтеплообмінні труби
dc.subjectкорозійні дефекти
dc.subjectвихорострумовий аналіз
dc.subjectметалографічні дослідження
dc.subjectsteam generator
dc.subjectheat-exchanging tubes
dc.subjectcorrosion defects
dc.subjecteddy-current testing
dc.subjectmetallographic examinations
dc.titleAnalysis of eddy-current testing and metallographic examinations for corrosion damages of heat exchanging tubes in NPP steam generators
dc.title.alternativeАналіз результатів вихорострумового контролю та металографічних досліджень корозійних дефектів теплообмінних труб парогенераторів АЕС
dc.typeArticle

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Energy Engineering and Control Systems. – 2020. – Vol. 6, No. 1