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Experimental study of interactions between suboxidized corium and reactor vessel steel
Alexandrov Research Institute of Technology (NITI).ORCID iD: 0000-0001-7816-8442
A.P. Aleksandrov Research Institute of Technology.
Alexandrov Research Institute of Technologies (NITI).
A.P. Aleksandrov Research Institute of Technology.
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2006 (English)In: Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, 2006, Vol. 2006, 1355-1362 p.Conference paper (Refereed)
Abstract [en]

One of the critical factors in the analysis of in-vessel melt retention is the vessel strength. It is, in particular, sensitive to the thickness of intact vessel wall, which, in its turn, depends on the thermal conditions and physicochemical interactions with corium. Physicochemical interaction of prototypic UO2-ZrO2-Zr corium melt and VVER vessel steel was examined during the 2nd Phase of the ISTC METCOR Project. Rasplav-3 test facility was used for conducting four tests, in which the Zr oxidation degree and interaction front temperature were varied; in one of the tests, stainless steel was added to the melt. Direct experimental measurements and posttest analyses were used for determining corrosion kinetics and maximum corrosion depth (i.e. the physicochemical impact of corium on the cooled vessel steel specimens), as well as the steel temperature conditions during the interaction, and finally the structure and composition of crystallized ingots, including the interaction zone. The minimum temperature on the interaction front boundary, which determined its final position and maximum corrosion depth was ∼ 1090°C. An empirical correlation for calculation of corrosion kinetics has been derived.

Place, publisher, year, edition, pages
2006. Vol. 2006, 1355-1362 p.
Keyword [en]
Core disruptive accidents, Corrosion prevention, Crystallization, Fission products, Steel ingots, Uranium dioxide, Physicochemical interactions, Reactor vessel steel, Suboxidized corium, Vessel melt retention, Reactor cores
National Category
Energy Engineering
URN: urn:nbn:se:kth:diva-53280ISBN: 0894486985ISBN: 978-089448698-2OAI: diva2:469816
American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06; Reno, NV; 4 June 2006 through 8 June 2006
QC 20111228Available from: 2011-12-27 Created: 2011-12-26 Last updated: 2012-01-21Bibliographically approved

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Bechta, Sevostian
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