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Sensitivity and uncertainty analysis of the vessel lower head failure mode and melt release conditions in Nordic BWR using MELCOR code
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet. KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnenergiteknik.ORCID-id: 0000-0001-8216-9376
KTH, Skolan för teknikvetenskap (SCI), Fysik, Kärnkraftssäkerhet.ORCID-id: 0000-0002-0683-9136
2020 (Engelska)Ingår i: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 135, artikel-id 106976Artikel i tidskrift (Refereegranskat) Published
Abstract [en]

Nordic boiling water reactors (BWR) employ ex-vessel debris coolability as a severe accident management (SAM) strategy. Melt release mode into a deep water pool located in the lower drywell is a major source of uncertainty for success of such strategy. The main goal of this work is to identify the major contributors to the uncertainty in prediction of vessel failure mode, timing and melt release conditions in Nordic BWR using MELCOR severe accident analysis code. There is a forest of control rod guide tubes (CRGTs) and instrumentation guide tubes (IGTs) in the lower head of a BWR. Failure of the penetrations is considered in this work along with the gross creep rupture of the vessel lower head. Modelling of penetrations failure in MELCOR code is based on parametric models, allowing a user to select different assumptions, such as temperature threshold for penetrations failure, modelling of penetrations assembly and respective failure modes, mode of solid and liquid debris ejection from the vessel. In this work we perform sensitivity analysis to the MELCOR modelling options and sensitivity parameters in unmitigated station blackout scenario (SBO). Results of analysis suggest that (i) vessel breach due to penetration failure is predicted to occur before creep-rupture failure of the vessel lower head, (ii) the mode of debris ejection from the vessel has the dominant effect on the likelihood of creep-rupture failure of the vessel lower head and debris ejection rate from the vessel.

Ort, förlag, år, upplaga, sidor
Elsevier Ltd , 2020. Vol. 135, artikel-id 106976
Nyckelord [en]
MELCOR, Melt release, Nordic BWR, Sensitivity, Uncertainty, Vessel failure, Accidents, Boiling water reactors, Codes (symbols), Creep, Debris, Failure modes, Sensitivity analysis, Uncertainty analysis, Failure (mechanical)
Nationell ämneskategori
Energiteknik Annan fysik
Forskningsämne
Fysik, Kärnenergiteknik
Identifikatorer
URN: urn:nbn:se:kth:diva-263441DOI: 10.1016/j.anucene.2019.106976ISI: 000496898500044Scopus ID: 2-s2.0-85070926736OAI: oai:DiVA.org:kth-263441DiVA, id: diva2:1375564
Forskningsfinansiär
Strålsäkerhetsmyndigheten
Anmärkning

QC 20191205

Tillgänglig från: 2019-12-05 Skapad: 2019-12-05 Senast uppdaterad: 2019-12-17Bibliografiskt granskad

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Galushin, SergeyKudinov, Pavel

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Annals of Nuclear Energy
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