Change search
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention
Show others and affiliations
2018 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 327, p. 82-91Article in journal (Refereed) Published
Abstract [en]

The paper presents some results of the ISTC (International Science and Technology Center)-financed project ‘Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel’ (METCOR). In the METCOR experiments the metallic phase of a two-liquid system was produced by the interaction between hot suboxidized corium and cooled VVER vessel steel, with the steel being corroded. Models of corrosion mechanisms in the considered conditions are used to systematize data on the limiting temperature of corrosion/(dissolution) of the vessel steel. A considerable influence of thermal gradient conditions is shown, which has to be taken into account in the analysis of molten pool behaviour. 

Place, publisher, year, edition, pages
Elsevier Ltd , 2018. Vol. 327, p. 82-91
Keywords [en]
Chemical elements, Corrosion, Nuclear reactors, Thermal gradients, Corrosion mechanisms, Effect of temperature, Element partitioning, In-vessel retention, International science, Limiting temperature, Reactor vessel steel, Two-liquid systems, Temperature
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-223155DOI: 10.1016/j.nucengdes.2017.11.030ISI: 000425302400008Scopus ID: 2-s2.0-85038017789OAI: oai:DiVA.org:kth-223155DiVA, id: diva2:1190405
Note

Export Date: 13 February 2018; Article; CODEN: NEDEA; Correspondence Address: Bottomley, D.; Invited Researcher at JAEA/CLADSJapan; email: dboksb3@gmail.com; Funding details: ISTC, International Science and Technology Center. QC 20180314

Available from: 2018-03-14 Created: 2018-03-14 Last updated: 2018-03-14Bibliographically approved

Open Access in DiVA

No full text in DiVA

Other links

Publisher's full textScopus

Authority records BETA

Bechta, Sevostian

Search in DiVA

By author/editor
Bechta, Sevostian
By organisation
Nuclear Power Safety
In the same journal
Nuclear Engineering and Design
Physical Sciences

Search outside of DiVA

GoogleGoogle Scholar

doi
urn-nbn

Altmetric score

doi
urn-nbn
Total: 36 hits
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf