Ändra sökning
RefereraExporteraLänk till posten
Permanent länk

Direktlänk
Referera
Referensformat
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Annat format
Fler format
Språk
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Annat språk
Fler språk
Utmatningsformat
  • html
  • text
  • asciidoc
  • rtf
Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0001-8216-9376
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0002-0683-9136
2019 (Engelska)Ingår i: Science and Technology of Nuclear Installations, ISSN 1687-6075, E-ISSN 1687-6083, artikel-id 5310808Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

Nordic Boiling Water Reactors (BWRs) employ ex-vessel debris coolability as a severe accident management strategy (SAM). Core melt is released into a deep pool of water where formation of noncoolable debris bed and ex-vessel steam explosion can pose credible threats to containment integrity. Success of the strategy depends on the scenario of melt release from the vessel that determines the melt-coolant interaction phenomena. The melt release conditions are determined by the in-vessel phase of severe accident progression. Specifically, properties of debris relocated into the lower plenum have influence on the vessel failure and melt release mode. In this work we use MELCOR code for prediction of the relocated debris. Over the years, many code modifications have been made to improve prediction of severe accident progression in light-water reactors. The main objective of this work is to evaluate the effect of models and best practices in different versions of MELCOR code on the in-vessel phase of different accident progression scenarios in Nordic BWR. The results of the analysis show that the MELCOR code versions 1.86 and 2.1 generate qualitatively similar results. Significant discrepancy in the timing of the core support failure and relocated debris mass in the MELCOR 2.2 compared to the MELCOR 1.86 and 2.1 has been found for a domain of scenarios with delayed time of depressurization. The discrepancies in the results can be explained by the changes in the modeling of degradation of the core components and changes in the Lipinski dryout model in MELCOR 2.2.

Ort, förlag, år, upplaga, sidor
Hindawi Publishing Corporation, 2019. artikel-id 5310808
Nationell ämneskategori
Fysik
Identifikatorer
URN: urn:nbn:se:kth:diva-251723DOI: 10.1155/2019/5310808ISI: 000466590400001Scopus ID: 2-s2.0-85065230309OAI: oai:DiVA.org:kth-251723DiVA, id: diva2:1316619
Anmärkning

QC 20190520

Tillgänglig från: 2019-05-20 Skapad: 2019-05-20 Senast uppdaterad: 2019-05-29Bibliografiskt granskad

Open Access i DiVA

Fulltext saknas i DiVA

Övriga länkar

Förlagets fulltextScopus

Personposter BETA

Galushin, SergeyKudinov, Pavel

Sök vidare i DiVA

Av författaren/redaktören
Galushin, SergeyKudinov, Pavel
Av organisationen
Kärnkraftssäkerhet
I samma tidskrift
Science and Technology of Nuclear Installations
Fysik

Sök vidare utanför DiVA

GoogleGoogle Scholar

doi
urn-nbn

Altmetricpoäng

doi
urn-nbn
Totalt: 12 träffar
RefereraExporteraLänk till posten
Permanent länk

Direktlänk
Referera
Referensformat
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Annat format
Fler format
Språk
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Annat språk
Fler språk
Utmatningsformat
  • html
  • text
  • asciidoc
  • rtf