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INTERACTION BETWEEN...
INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL
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- Bechta, Sevostian (author)
- Alexandrov Scientific-Research Technology Institute, Sosnovy Bor
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- Granovsky, V.S. (author)
- Alexandrov Research Institute of Technologies (NITI)
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- Khabensky, V.B. (author)
- A.P. Aleksandrov Research Institute of Technology
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- Krushinov, E.V. (author)
- A.P. Aleksandrov Research Institute of Technology
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- Vitol, S.A (author)
- A.P. Aleksandrov Research Institute of Technology
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- Sulatsky, A.A. (author)
- Alexandrov Scientific-Research Institute of Technology
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- Gusarov, V.V. (author)
- Institute of Silicate Chemistry of Russian Academy of Sciences
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- Almjashev, V.I. (author)
- Institute of Silicate Chemistry of Russian Academy of Sciences
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- Lopukh, D.B. (author)
- Saint-Petersburg Electrotechnical University ‘LETI’
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- Bottomley, D. (author)
- European Commission – DG – Joint Research Centre, Institute for Transuranium Elements
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- Fischer, M. (author)
- Framatome ANP GmbH
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- Piluso, P. (author)
- CEA/DEN/DSNI, Bbt. 121, 91191 Gif sur Yvette Cedex, Saclay, France
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- Miassoedov, A. (author)
- Institute for Nuclear and Energy Technologies, Forschungszentrum Karlsruhe
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- Tromm, W. (author)
- FZK, IKET, Karlsruhe, Forschungszentrum Karlsruhe GmbH
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- Altstadt, E. (author)
- Forschungszentrum Rossendorf (FZR), 01328 Dresden, Germany
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- Fichot, F. (author)
- Institut de Radioprotection et Sûreté Nucléaire IRSN/DPAM
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- Kymaelaeinen, O. (author)
- Fortum Nuclear Services Ltd, POB 10, FIN-00048 Fortum (Finland)
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(creator_code:org_t)
- American Nuclear Society, 2010
- 2010
- English.
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In: Nuclear Technology. - : American Nuclear Society. - 0029-5450 .- 1943-7471. ; 170:1, s. 210-218
- Related links:
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http://www.new.ans.o...
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https://urn.kb.se/re...
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Abstract
Subject headings
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- In case of in-vessel corium retention during a severe accident in a light water reactor, weakening of the vessel wall and deterioration of the vessel steel properties can be caused both by the melting of the steel and by its physicochemical interaction with corium. The interaction behavior has been studied in medium-scale experiments with prototypic corium. The experiments yielded data for the steel corrosion rate during interaction with UO2+x-ZrO2-FeOy melt in air and steam at different steel surface temperatures and heat fluxes from the corium to the steel. It has been observed that the corrosion rates in air and steam atmosphere are almost the same. Further, if the temperature at the interface increases beyond a certain level, corrosion intensifies. This is explained by the formation of liquid phases in the interaction zone. The available experimental data have been used to develop a correlation for the corrosion rate as afunction of temperature and heat flux.
Subject headings
- TEKNIK OCH TEKNOLOGIER -- Maskinteknik -- Energiteknik (hsv//swe)
- ENGINEERING AND TECHNOLOGY -- Mechanical Engineering -- Energy Engineering (hsv//eng)
Keyword
- Zirconium oxide
- Uranium dioxide
- Heat flux
- Meltdown
- Corrosion
- Nuclear reactor
- Light water reactor
- Accident
- Pressurized water reactor
Publication and Content Type
- ref (subject category)
- art (subject category)
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- By the author/editor
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Bechta, Sevostia ...
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Granovsky, V.S.
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Khabensky, V.B.
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Krushinov, E.V.
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Vitol, S.A
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Sulatsky, A.A.
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show more...
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Gusarov, V.V.
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Almjashev, V.I.
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Lopukh, D.B.
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Bottomley, D.
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Fischer, M.
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Piluso, P.
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Miassoedov, A.
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Tromm, W.
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Altstadt, E.
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Fichot, F.
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Kymaelaeinen, O.
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show less...
- About the subject
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- ENGINEERING AND TECHNOLOGY
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ENGINEERING AND ...
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and Mechanical Engin ...
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and Energy Engineeri ...
- Articles in the publication
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Nuclear Technolo ...
- By the university
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Royal Institute of Technology