Analysis of the Effect of Pollution of Component Surfaces as a Result of Possible Contact of Fresh Nuclear Fuel with Sea Atmosphere on Corrosion

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dc.citation.epage21
dc.citation.issue1
dc.citation.journalTitleЕнергетика та системи керування
dc.citation.spage17
dc.contributor.affiliationНаціональний університет “Львівська політехніка”
dc.contributor.affiliationLviv Polytechnic National University
dc.contributor.authorЛис, Степан
dc.contributor.authorLys, Stepan
dc.coverage.placenameЛьвів
dc.coverage.placenameLviv
dc.date.accessioned2024-02-08T08:27:44Z
dc.date.available2024-02-08T08:27:44Z
dc.date.created2023-02-28
dc.date.issued2023-02-28
dc.description.abstractиконано збирання та аналізування інформації щодо можливого впливу компонентів морської атмосфери у разі забруднення ними поверхні збірок на корозію конструкційних матеріалів деталей тепловидільних збірок водо-водяного енергетичного реактора ВВЕР-1000 за їх подальшої експлуатації. Наведено дані статичних і динамічних випробувань сплаву Е-110 за температур 300–350 С у воді та у штатному теплоносії реакторів, забруднених хлоридами і йодом, а також сплаву Е-110 за спеціального забруднення його поверхні хлоридами. Показано, що у разі дотримання умов зберігання свіжого палива, а також рекомендацій цієї роботи забезпечується його висока корозійна стійкість і працездатність під час подальшої експлуатації.
dc.description.abstractAcquisition and analysis of the information was performed on possible effect of components of sea atmosphere in case of their precipitation on the assembly surfaces on the corrosion of structural materials of items of fuel assemblies (FAs) of water-water energetic reactor (VVER-1000) in their subsequent operation. The data is presented on static and dynamic tests of alloy E-110 at temperatures of 300–350 °С in water and standard coolant of the reactor polluted with chlorides and iodine, as well as of alloy E-110 under special pollution of its surface with chlorides. It is demonstrated that in keeping the conditions of storage of fresh fuel, as well as the recommendations of the present work, its high corrosion resistance and operability in further operation is ensured.
dc.format.extent17-21
dc.format.pages5
dc.identifier.citationLys S. Analysis of the Effect of Pollution of Component Surfaces as a Result of Possible Contact of Fresh Nuclear Fuel with Sea Atmosphere on Corrosion / Stepan Lys // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2023. — Vol 9. — No 1. — P. 17–21.
dc.identifier.citationenLys S. Analysis of the Effect of Pollution of Component Surfaces as a Result of Possible Contact of Fresh Nuclear Fuel with Sea Atmosphere on Corrosion / Stepan Lys // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2023. — Vol 9. — No 1. — P. 17–21.
dc.identifier.doidoi.org/10.23939/jeecs2023.01.017
dc.identifier.urihttps://ena.lpnu.ua/handle/ntb/61153
dc.language.isoen
dc.publisherВидавництво Львівської політехніки
dc.publisherLviv Politechnic Publishing House
dc.relation.ispartofЕнергетика та системи керування, 1 (9), 2023
dc.relation.ispartofEnergy Engineering and Control Systems, 1 (9), 2023
dc.relation.references[1] Cox, B. (1973) Stress corrosion of zirconium alloys in neutral chloride. Corrosion. Vol. 29. No. 4. p. 157.
dc.relation.references[2] Kosinov, V. A., Kuchin, O. P., Novikov, O. K., Osharina, L. V., Fedenko, V. I. (1983) Corrosion of alloy Zr – 1 % Nb in distilled water containing ions of Cl or F at temperature 300 °С, IATF specialists meetings on “Influence of water chemistry on fuel element cladding behaviour in water cooled power reactors”. Leningrad / USSR/ 6-10 June 1983. /IWGFPT/ 17. IAEA/ Vienna.
dc.relation.references[3] Gerasimov, V. V., Gerasimova, V. V. (1989) Chloride and iodide corrosion of zirconium alloys. Pre-print. M., TSNIIatominform (in Russian).
dc.relation.references[4] Knittel, D. R. (1982) The effect of surface treatment on pitting potentials of zirconium in chloride solution. Corrosion. Vol. 38, No. 5, p. 140.
dc.relation.references[5] Gerasimov, V. V. (1980) Corrosion of reactor materials., М., Atomizdat (in Russian).
dc.relation.references[6] Migay, L. L., Taritsina, T. A. (1988) Corrosion resistance of materials in halogens and their compounds. M.: Chemistry (in Russian).
dc.relation.references[7] Preliminary safety analysis reports. Topical report. Development of recommendations on storage of fresh fuel within five years. Justification of requirements for storage atmosphere, 412-312-О-10, KK.UJA.JKA.TM.TR.PR033, 2001.
dc.relation.references[8] Semerak, M. M., Lys, S. S. (2021). Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident. Problems of atomic science and technology, Kharkiv, No. 2 (132), 80–86. https://doi.org/10.46813/2021-132-080.
dc.relation.references[9] Kalman, I. G. (1971). Effect of environmental factors on hardware and components. Methods of climatic tests. М., Znanie (in Russian).
dc.relation.references[10] Stepan Lys, Alexander Kanyuka (2021). Analysis of fuel rod performance per cycle: Temperature field, FGP release, swelling. Thermal Science and Engineering Progress, Vol. 25, 100961. https://doi.org/10.1016/j.tsep.2021.100961.
dc.relation.references[11] Stepan Lys, Alexandr Kanyuka (2022). Algorithms for processing self-powered neutron detector signals important for determination of local parameters in each part of the VVER core EPJ Nuclear Sci. Technol. 8, 17. https://doi.org/10.1051/epjn/2022008.
dc.relation.references[12] Lys, S. S., Semerak, M. M., Kanyuka, A. I. (2021). Analysis of reliability of automatic core protection function of the reactor V-412 in response to local parameters: maximum linear power, departure from nucleate boiling ratio. Problems of atomic science and technology. Kharkiv, No. 5(135), 88–97. https://doi.org/10.46813/2021-135-088.
dc.relation.referencesen[1] Cox, B. (1973) Stress corrosion of zirconium alloys in neutral chloride. Corrosion. Vol. 29. No. 4. p. 157.
dc.relation.referencesen[2] Kosinov, V. A., Kuchin, O. P., Novikov, O. K., Osharina, L. V., Fedenko, V. I. (1983) Corrosion of alloy Zr – 1 % Nb in distilled water containing ions of Cl or F at temperature 300 °S, IATF specialists meetings on "Influence of water chemistry on fuel element cladding behaviour in water cooled power reactors". Leningrad, USSR/ 6-10 June 1983. /IWGFPT/ 17. IAEA/ Vienna.
dc.relation.referencesen[3] Gerasimov, V. V., Gerasimova, V. V. (1989) Chloride and iodide corrosion of zirconium alloys. Pre-print. M., TSNIIatominform (in Russian).
dc.relation.referencesen[4] Knittel, D. R. (1982) The effect of surface treatment on pitting potentials of zirconium in chloride solution. Corrosion. Vol. 38, No. 5, p. 140.
dc.relation.referencesen[5] Gerasimov, V. V. (1980) Corrosion of reactor materials., M., Atomizdat (in Russian).
dc.relation.referencesen[6] Migay, L. L., Taritsina, T. A. (1988) Corrosion resistance of materials in halogens and their compounds. M., Chemistry (in Russian).
dc.relation.referencesen[7] Preliminary safety analysis reports. Topical report. Development of recommendations on storage of fresh fuel within five years. Justification of requirements for storage atmosphere, 412-312-O-10, KK.UJA.JKA.TM.TR.PR033, 2001.
dc.relation.referencesen[8] Semerak, M. M., Lys, S. S. (2021). Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident. Problems of atomic science and technology, Kharkiv, No. 2 (132), 80–86. https://doi.org/10.46813/2021-132-080.
dc.relation.referencesen[9] Kalman, I. G. (1971). Effect of environmental factors on hardware and components. Methods of climatic tests. M., Znanie (in Russian).
dc.relation.referencesen[10] Stepan Lys, Alexander Kanyuka (2021). Analysis of fuel rod performance per cycle: Temperature field, FGP release, swelling. Thermal Science and Engineering Progress, Vol. 25, 100961. https://doi.org/10.1016/j.tsep.2021.100961.
dc.relation.referencesen[11] Stepan Lys, Alexandr Kanyuka (2022). Algorithms for processing self-powered neutron detector signals important for determination of local parameters in each part of the VVER core EPJ Nuclear Sci. Technol. 8, 17. https://doi.org/10.1051/epjn/2022008.
dc.relation.referencesen[12] Lys, S. S., Semerak, M. M., Kanyuka, A. I. (2021). Analysis of reliability of automatic core protection function of the reactor V-412 in response to local parameters: maximum linear power, departure from nucleate boiling ratio. Problems of atomic science and technology. Kharkiv, No. 5(135), 88–97. https://doi.org/10.46813/2021-135-088.
dc.relation.urihttps://doi.org/10.46813/2021-132-080
dc.relation.urihttps://doi.org/10.1016/j.tsep.2021.100961
dc.relation.urihttps://doi.org/10.1051/epjn/2022008
dc.relation.urihttps://doi.org/10.46813/2021-135-088
dc.rights.holder© Національний університет “Львівська політехніка”, 2023
dc.subjectреактор
dc.subjectоболонковий цирконієвий сплав Е-110
dc.subjectкорозія
dc.subjectморська атмосфера
dc.subjectстандартна охолоджувальна рідина
dc.subjectзабруднення теплоносія
dc.subjectreactor
dc.subjectclad zirconium alloy E-110
dc.subjectcorrosion
dc.subjectsea atmosphere
dc.subjectstandard coolant
dc.subjectcoolant pollution
dc.titleAnalysis of the Effect of Pollution of Component Surfaces as a Result of Possible Contact of Fresh Nuclear Fuel with Sea Atmosphere on Corrosion
dc.title.alternativeАналіз впливу забруднень поверхні деталей у результаті можливого контакту свіжого ядерного палива з морською атмосферою на корозію
dc.typeArticle

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Energy Engineering and Control Systems. – 2023. – Vol. 9, No. 1