Search: L773:0029 5450 OR L773:1943 7471 > (2010-2014) > INTERACTION BETWEEN...
Fältnamn | Indikatorer | Metadata |
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000 | 04074naa a2200577 4500 | |
001 | oai:DiVA.org:kth-53474 | |
003 | SwePub | |
008 | 111228s2010 | |||||||||||000 ||eng| | |
024 | 7 | a 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 | 7 | a ref2 swepub-contenttype |
072 | 7 | a art2 swepub-publicationtype |
100 | 1 | a Bechta, Sevostianu Alexandrov Scientific-Research Technology Institute, Sosnovy Bor4 aut0 (Swepub:kth)u1jwt3ck |
245 | 1 0 | a INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL |
264 | 1 | b 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 | 7 | a TEKNIK OCH TEKNOLOGIERx Maskinteknikx Energiteknik0 (SwePub)203042 hsv//swe |
650 | 7 | a 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 | |
700 | 1 | a Granovsky, V.S.u Alexandrov Research Institute of Technologies (NITI)4 aut |
700 | 1 | a Khabensky, V.B.u A.P. Aleksandrov Research Institute of Technology4 aut |
700 | 1 | a Krushinov, E.V.u A.P. Aleksandrov Research Institute of Technology4 aut |
700 | 1 | a Vitol, S.Au A.P. Aleksandrov Research Institute of Technology4 aut |
700 | 1 | a Sulatsky, A.A.u Alexandrov Scientific-Research Institute of Technology4 aut |
700 | 1 | a Gusarov, V.V.u Institute of Silicate Chemistry of Russian Academy of Sciences4 aut |
700 | 1 | a Almjashev, V.I.u Institute of Silicate Chemistry of Russian Academy of Sciences4 aut |
700 | 1 | a Lopukh, D.B.u Saint-Petersburg Electrotechnical University ‘LETI’4 aut |
700 | 1 | a Bottomley, D.u European Commission – DG – Joint Research Centre, Institute for Transuranium Elements4 aut |
700 | 1 | a Fischer, M.u Framatome ANP GmbH4 aut |
700 | 1 | a Piluso, P.u CEA/DEN/DSNI, Bbt. 121, 91191 Gif sur Yvette Cedex, Saclay, France4 aut |
700 | 1 | a Miassoedov, A.u Institute for Nuclear and Energy Technologies, Forschungszentrum Karlsruhe4 aut |
700 | 1 | a Tromm, W.u FZK, IKET, Karlsruhe, Forschungszentrum Karlsruhe GmbH4 aut |
700 | 1 | a Altstadt, E.u Forschungszentrum Rossendorf (FZR), 01328 Dresden, Germany4 aut |
700 | 1 | a Fichot, F.u Institut de Radioprotection et Sûreté Nucléaire IRSN/DPAM4 aut |
700 | 1 | a Kymaelaeinen, O.u Fortum Nuclear Services Ltd, POB 10, FIN-00048 Fortum (Finland)4 aut |
710 | 2 | a Alexandrov Scientific-Research Technology Institute, Sosnovy Borb Alexandrov Research Institute of Technologies (NITI)4 org |
773 | 0 | t Nuclear Technologyd : American Nuclear Societyg 170:1, s. 210-218q 170:1<210-218x 0029-5450x 1943-7471 |
856 | 4 | u http://www.new.ans.org.focus.lib.kth.se/store/j_9459 |
856 | 4 8 | u https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-53474 |
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