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Search: L773:0029 5450 OR L773:1943 7471 > (2010-2014) > INTERACTION BETWEEN...

LIBRIS Formathandbok  (Information om MARC21)
FältnamnIndikatorerMetadata
00004074naa a2200577 4500
001oai:DiVA.org:kth-53474
003SwePub
008111228s2010 | |||||||||||000 ||eng|
024a https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-534742 URI
040 a (SwePub)kth
041 a engb eng
042 9 SwePub
072 7a ref2 swepub-contenttype
072 7a art2 swepub-publicationtype
100a Bechta, Sevostianu Alexandrov Scientific-Research Technology Institute, Sosnovy Bor4 aut0 (Swepub:kth)u1jwt3ck
2451 0a INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL
264 1b American Nuclear Society,c 2010
338 a print2 rdacarrier
500 a QC 20120110
520 a 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.
650 7a TEKNIK OCH TEKNOLOGIERx Maskinteknikx Energiteknik0 (SwePub)203042 hsv//swe
650 7a ENGINEERING AND TECHNOLOGYx Mechanical Engineeringx Energy Engineering0 (SwePub)203042 hsv//eng
653 a Zirconium oxide
653 a Uranium dioxide
653 a Heat flux
653 a Meltdown
653 a Corrosion
653 a Nuclear reactor
653 a Light water reactor
653 a Accident
653 a Pressurized water reactor
700a Granovsky, V.S.u Alexandrov Research Institute of Technologies (NITI)4 aut
700a Khabensky, V.B.u A.P. Aleksandrov Research Institute of Technology4 aut
700a Krushinov, E.V.u A.P. Aleksandrov Research Institute of Technology4 aut
700a Vitol, S.Au A.P. Aleksandrov Research Institute of Technology4 aut
700a Sulatsky, A.A.u Alexandrov Scientific-Research Institute of Technology4 aut
700a Gusarov, V.V.u Institute of Silicate Chemistry of Russian Academy of Sciences4 aut
700a Almjashev, V.I.u Institute of Silicate Chemistry of Russian Academy of Sciences4 aut
700a Lopukh, D.B.u Saint-Petersburg Electrotechnical University ‘LETI’4 aut
700a Bottomley, D.u European Commission – DG – Joint Research Centre, Institute for Transuranium Elements4 aut
700a Fischer, M.u Framatome ANP GmbH4 aut
700a Piluso, P.u CEA/DEN/DSNI, Bbt. 121, 91191 Gif sur Yvette Cedex, Saclay, France4 aut
700a Miassoedov, A.u Institute for Nuclear and Energy Technologies, Forschungszentrum Karlsruhe4 aut
700a Tromm, W.u FZK, IKET, Karlsruhe, Forschungszentrum Karlsruhe GmbH4 aut
700a Altstadt, E.u Forschungszentrum Rossendorf (FZR), 01328 Dresden, Germany4 aut
700a Fichot, F.u Institut de Radioprotection et Sûreté Nucléaire IRSN/DPAM4 aut
700a Kymaelaeinen, O.u Fortum Nuclear Services Ltd, POB 10, FIN-00048 Fortum (Finland)4 aut
710a Alexandrov Scientific-Research Technology Institute, Sosnovy Borb Alexandrov Research Institute of Technologies (NITI)4 org
773t Nuclear Technologyd : American Nuclear Societyg 170:1, s. 210-218q 170:1<210-218x 0029-5450x 1943-7471
856u http://www.new.ans.org.focus.lib.kth.se/store/j_9459
8564 8u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-53474

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