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Comparison of melcor code versions predictions of the properties of relocated debris in lower plenum of nordic BWR
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. In this work we perform comparison of predictions of different MELCOR code versions used for the analysis of the effect severe accident scenario and uncertainties on the processes of core degradation and relocation, and resulting properties of relocated debris in Nordic BWR lower plenum. Properties of relocated debris are obtained as functions of the accident scenario parameters, such as timing of activation of different safety systems. We perform the analysis of the codes predictions and discuss possible reasons for the discrepancies in observations. The main goal of this work is to provide insights regarding the effect of code uncertainty, sensitivity coefficients and user effect on the code predictions, which is of 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-234524Scopus ID: 2-s2.0-85052503219OAI: oai:DiVA.org:kth-234524DiVA, id: diva2:1246436
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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