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Simulation of a Steam Bubble Transport in the Primary System of the Pool Type Lead Cooled Fast Reactors
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0002-0683-9136
2011 (English)In:  , 2011Conference paper (Refereed)
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Energy Engineering
URN: urn:nbn:se:kth:diva-53501OAI: diva2:470177
The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
QC 20120208Available from: 2011-12-28 Created: 2011-12-28 Last updated: 2012-02-08Bibliographically approved

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Jeltsov, MartiKudinov, Pavel
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