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Pre-test analysis of an LBE solidification experiment in TALL-3D
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-5653-9206
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0003-1213-0032
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-0683-9136
2018 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 339, p. 21-38Article in journal (Refereed) Published
Abstract [en]

Coolant solidification is a phenomenon of potential safety importance for Liquid Metal Cooled Fast Reactors (LMFRs). Coolant solidification can affect local flow, heat transfer and lead to partial or complete blockage of the coolant flow paths jeopardizing decay heat removal function. It is also possible that reduced flow circulation may increase coolant temperature, counteract solidification and prevent complete blockage of the flow. Complex interactions between local physical phenomena of solidification and system scale natural circulation make modelling of solidification uncertain. Development and validation of adequate models requires validation grade experimental data. In this work we discuss results of analysis carried out in support of experiment development, specifically, design of a solidification test section and a test matrix for TALL-3D experimental facility (lead-bismuth eutectic (LBE) thermal-hydraulic loop). The aim of the analysis is experimental design that satisfies requirements stemming from the process of model qualification. We focus on two aspects: (i) design of solidification test section (STS) for investigation of solidification phenomena in lead-bismuth eutectic (LBE), and (ii) effect of the STS pool on the system scale behavior of the TALL-3D facility. Selection of the STS characteristics and experimental test matrix is supported using computational fluid dynamic (CFD) and system thermal-hydraulic (STH) codes. 

Place, publisher, year, edition, pages
Elsevier Ltd , 2018. Vol. 339, p. 21-38
Keywords [en]
CFD, Coolant solidification, Experiment design, LMFR, STH, Bismuth, Computational fluid dynamics, Coolants, Design of experiments, Eutectics, Fast reactors, Heat transfer, Liquid metal cooled reactors, Testing, Coolant temperature, Experimental facilities, Lead-bismuth eutectics, Liquid-metal-cooled fast reactors, Natural circulation, Thermal hydraulics, Solidification
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-236566DOI: 10.1016/j.nucengdes.2018.08.014ISI: 000446333700003Scopus ID: 2-s2.0-85052758449OAI: oai:DiVA.org:kth-236566DiVA, id: diva2:1266107
Note

 Funding details: STS, Society of Thoracic Surgeons; Funding text: This work has received funding the Euratom research and training programme 2014–2018 under the grant agreement No. 654935 (SESAME). The authors are also thankful to Vincent Moreau and Manuela Profir for their contribution in the discussions and support during the STS design process. QC 20181127

Available from: 2018-11-27 Created: 2018-11-27 Last updated: 2018-11-27Bibliographically approved

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Jeltsov, MartiKööp, KasparGrishchenko, DmitryKudinov, Pavel

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