Analysis of computer modelling results on fuel rods strength and condition at reduced or absent cooling caused by accident

Simple item page
dc.citation.epage16
dc.citation.issue1
dc.citation.spage7
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.accessioned2023-09-14T07:39:55Z
dc.date.available2023-09-14T07:39:55Z
dc.date.created2021-06-01
dc.date.issued2021-06-01
dc.description.abstractУ статті представлена феноменологія поведінки твелів у важкій аварії. Як приклад наведено опис експерименту з важким пошкодженням 19-твельної збірки типу ВВЕР, проведеного на установці CORA (Дослідницький Центр Карлсруе, Німеччина). Представлені умови випробування і результати посттестових досліджень збірки. Наведено короткий опис твельного коду RAPTA-SFD, який брав участь у Міжнародній Стандартній Проблемі ISP-36. Представлені основні результати розрахункового моделювання експерименту CORA-W2 з використанням коду RAPTA-SFD. Серед представлених експериментально-розрахункових результатів значне місце займають дані щодо поведінки елементів з нержавіючої сталі. Конструкція випробуваної в експерименті CORA-W2 збірки містила значну кількість сталевих елементів: дистанціюючі решітки, направляючий канал, оболонка поглинаючого елемента. Дистанціюючі решітки і направляючий канал сучасної удосконаленої тепловиділяючої збірки (УТВЗ) ВВЕР-1000 виготовляються з цирконієвого сплаву, тому відносні кількісні характеристики хімічних взаємодій матеріалів з нержавіючої сталі для сучасної УТВЗ в аналогічних умовах будуть значно нижчі.
dc.description.abstractThe paper describes the phenomenology of fuel rod behaviour in severe accident. As an example, an experiment is described resulting in severe damage of 19 fuel rod assembly of VVER type; it was carried out in the CORA facility in 1993 (Research Centre, Karlsruhe, Germany). Testing conditions and results of post-test investigations of fuel assembly are given. The fuel rod code RAPTA-SFD is briefly dealt with; the code was a participant in the International Standard Problem ISP-36. The basic results are presented acquired by computer modelling CORA-W2 experiment using RAPTA-SFD code. Among the presented experimentally acquired and calculated results, the scope of the data on stainless steel component behaviour is substantial. The tested CORA-W2 fuel assembly contained a significant quantity of steel components, viz., spacer grids, a guide thimble, and a cladding of an absorber element. It is to be borne in mind that the spacer grids and a guide thimble of the updated and upgraded fuel assembly of VVER1000 are fabricated from Zr-alloy, hence, the relative quantitative characteristics of chemical interactions between materials and stainless steel (Cr-Ni alloy) will be much lower for the up-to-date upgraded fuel assembly under identical conditions.
dc.format.extent7-16
dc.format.pages10
dc.identifier.citationLys S. Analysis of computer modelling results on fuel rods strength and condition at reduced or absent cooling caused by accident / Stepan Lys // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2021. — Vol 7. — No 1. — P. 7–16.
dc.identifier.citationenLys S. Analysis of computer modelling results on fuel rods strength and condition at reduced or absent cooling caused by accident / Stepan Lys // Energy Engineering and Control Systems. — Lviv : Lviv Politechnic Publishing House, 2021. — Vol 7. — No 1. — P. 7–16.
dc.identifier.urihttps://ena.lpnu.ua/handle/ntb/59985
dc.language.isoen
dc.publisherВидавництво Львівської політехніки
dc.publisherLviv Politechnic Publishing House
dc.relation.ispartofEnergy Engineering and Control Systems, 1 (7), 2021
dc.relation.references[1] Nuclear safety rules for nuclear power plants. PBYA RU AS-89. PNAE G-1-024-90. (in Russian)
dc.relation.references[2] General provisions for ensuring the safety of nuclear power plants OPB-88/97. NP-001-97 (PNAE G-01-011-97). Approved by the Resolution of the Gosatomnadzor of Russia N9 of 11/14/97. (in Russian)
dc.relation.references[3] Firnhaber M., Trambauer K., Hagen S., Hofmann P., Yegorova L. Specification of the International Standard Problem ISP36: CORA-W2 Experiment on Severe Fuel Damage. February 1994.
dc.relation.references[4] International Standard Problem ISP-36: CORA-W2 Experiment on Severe Fuel Damage for a Russian Type PWR. Comparison Report. OCDE/GD(96)19, GRS-120, FZKA 5711.
dc.relation.references[5] NPP “KUDANKULAM” Unit 1,2. Topical report “Results of computer modelling fuel rods strength and condition in accidents attended with deteriorated cooling or loss of coolant (postulation cladding temperature rise up to melting point)” SE VNIINM, 2001.
dc.relation.references[6] Bibilashvily Yu. K., Sokolov N. B., Salatov A. V., Andreyeva-Andrievskaya L. N., Nechaeva O. A., Vlasov F. Yu. Features of RAPTA-SFD code modelling of chemical interactions of basic materials of the VVER active zone in accident conditions with severe fuel damage. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October 1995. IAEA-TECDOC-921, Vienna, 1996, pp. 243–252.
dc.relation.references[7] Hofmann P., Uetsuka H., Wilhelm A.N., Garcia E.A. Dissolution of solid UO2 by molten zircaloy and its modelling. In: Severe Accidents in Nuclear Power Plants, Proceedings of a Symposium, Sorrento, 21–25 March 1988, Jointly organized by IAEA and NEA (OECD), IAEA-SM-296/1, pp. 3–17.
dc.relation.references[8] Goryachev A., Shtuckert Yu., Zwir E., Stupina L. Post-test investigation result on the VVER-1000 fuel tested under severe accident conditions. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October 1995. IAEA-TECDOC-921, Vienna, 1996, pp. 187–202.
dc.relation.referencesen[1] Nuclear safety rules for nuclear power plants. PBYA RU AS-89. PNAE G-1-024-90. (in Russian)
dc.relation.referencesen[2] General provisions for ensuring the safety of nuclear power plants OPB-88/97. NP-001-97 (PNAE G-01-011-97). Approved by the Resolution of the Gosatomnadzor of Russia N9 of 11/14/97. (in Russian)
dc.relation.referencesen[3] Firnhaber M., Trambauer K., Hagen S., Hofmann P., Yegorova L. Specification of the International Standard Problem ISP36: CORA-W2 Experiment on Severe Fuel Damage. February 1994.
dc.relation.referencesen[4] International Standard Problem ISP-36: CORA-W2 Experiment on Severe Fuel Damage for a Russian Type PWR. Comparison Report. OCDE/GD(96)19, GRS-120, FZKA 5711.
dc.relation.referencesen[5] NPP "KUDANKULAM" Unit 1,2. Topical report "Results of computer modelling fuel rods strength and condition in accidents attended with deteriorated cooling or loss of coolant (postulation cladding temperature rise up to melting point)" SE VNIINM, 2001.
dc.relation.referencesen[6] Bibilashvily Yu. K., Sokolov N. B., Salatov A. V., Andreyeva-Andrievskaya L. N., Nechaeva O. A., Vlasov F. Yu. Features of RAPTA-SFD code modelling of chemical interactions of basic materials of the VVER active zone in accident conditions with severe fuel damage. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October 1995. IAEA-TECDOC-921, Vienna, 1996, pp. 243–252.
dc.relation.referencesen[7] Hofmann P., Uetsuka H., Wilhelm A.N., Garcia E.A. Dissolution of solid UO2 by molten zircaloy and its modelling. In: Severe Accidents in Nuclear Power Plants, Proceedings of a Symposium, Sorrento, 21–25 March 1988, Jointly organized by IAEA and NEA (OECD), IAEA-SM-296/1, pp. 3–17.
dc.relation.referencesen[8] Goryachev A., Shtuckert Yu., Zwir E., Stupina L. Post-test investigation result on the VVER-1000 fuel tested under severe accident conditions. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October 1995. IAEA-TECDOC-921, Vienna, 1996, pp. 187–202.
dc.rights.holder© Національний університет “Львівська політехніка”, 2021
dc.subjectтепловиділяючий елемент
dc.subjectпоглинаючий елемент
dc.subjectважка аварія
dc.subjectхімічна взаємодія
dc.subjectдіоксид урану
dc.subjectfuel rod
dc.subjectabsorber
dc.subjectsevere accident
dc.subjectchemical interaction
dc.subjecturaniumdioxide
dc.titleAnalysis of computer modelling results on fuel rods strength and condition at reduced or absent cooling caused by accident
dc.title.alternativeАналіз результатів розрахункового моделювання міцності і стану твелів в умовах аварії з погіршеним або відсутнім охолодженням
dc.typeArticle

Files

Original bundle
Now showing 1 - 2 of 2
No Thumbnail Available
Name:
2021v7n1_Lys_S-Analysis_of_computer_modelling_7-16.pdf
Size:
863.76 KB
Format:
Adobe Portable Document Format
Download
No Thumbnail Available
Name:
2021v7n1_Lys_S-Analysis_of_computer_modelling_7-16__COVER.png
Size:
378.5 KB
Format:
Portable Network Graphics
Download
License bundle
Now showing 1 - 1 of 1
No Thumbnail Available
Name:
license.txt
Size:
1.76 KB
Format:
Plain Text
Description:
Download

Collections

Energy Engineering and Control Systems. – 2021. – Vol. 7, No. 1