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Coupled 1D-3D Thermal-Hydraulic Simulations of a Liquid Metal Experiment Supplemented by Uncertainty and Sensitivity Analysis
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-5653-9206
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2014 (English)In: OECD/NEA & IAEA Workshop: Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation, 2014Conference paper (Refereed)
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Energy Engineering
URN: urn:nbn:se:kth:diva-165401OAI: diva2:808239
CFD4NRS-5, OECD/NEA & IAEA Workshop, September 8, 2014 Friday September 12, 2014, Zürich, Switzerland

QC 20150430

Available from: 2015-04-27 Created: 2015-04-27 Last updated: 2015-04-30Bibliographically approved

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Jeltsov, MartiKööp, KasparKudinov, Pavel
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