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Effect of severe accident scenario and modeling options in melcor on the properties of relocated debris in nordic BWR lower plenum
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-8216-9376
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-0683-9136
2016 (English)In: 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery (ACM), 2016Conference paper, Published paper (Refereed)
Abstract [en]

Severe accident management (SAM) in Nordic Boiling Water Reactors (BWR) employs ex-vessel core debris coolability. Core melt is poured into a deep pool of water and is expected to fragment, quench, and form a coolable debris bed. Success of the strategy is contingent upon the vessel failure and melt release mode from the vessel, which determine conditions for (i) the formation of debris bed and its coolability, and (ii) steam explosion. Non-coolable debris and strong explosions present credible threats to containment integrity. A risk oriented accident analysis framework (ROAAM+) is under development for assessment of the effectiveness of the severe accident management strategy. The characteristics of melt release are determined by the in-vessel accident scenarios and phenomena subject to aleatory and epistemic uncertainties respectively. Specifically, properties of the debris relocated into the lower head determine conditions for the corium interactions with the vessel structures, vessel failure and melt release. This work is focused on the evaluation of uncertainty in core degradation progression and its effect on the resultant properties of relocated debris in lower plenum of Nordic BWR. We use MELCOR code for prediction of the accident progression. The main goal of this paper is to characterize the range of possible debris properties in lower plenum and its sensitivity towards different modelling parameters, which is of paramount importance for the analysis of in-vessel debris coolability and vessel failure mode in the ROAAM+ framework.

Place, publisher, year, edition, pages
Association for Computing Machinery (ACM), 2016.
Keywords [en]
MELCOR, Nordic BWR, Severe Accident
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-234523Scopus ID: 2-s2.0-85052524407OAI: oai:DiVA.org:kth-234523DiVA, id: diva2:1246363
Conference
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Qujiang Int'l Conference CenterXi'an, Shaanxi, China, 3 September 2017 through 8 September 2017
Note

QC 20180907

Available from: 2018-09-07 Created: 2018-09-07 Last updated: 2018-09-07Bibliographically approved

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Galushin, SergeyKudinov, Pavel

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