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Numerical Analysis of Reactor Scale Ex-vessel Fuel Coolant Interactions Phenomena Using MC3D Code
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.ORCID iD: 0000-0001-8001-9323
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2013 (English)Conference paper, Published paper (Refereed)
Place, publisher, year, edition, pages
2013. 446- p.
Keyword [en]
BWR, Fuel-coolant interactions, steam explosion
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-123694OAI: oai:DiVA.org:kth-123694DiVA: diva2:628601
Conference
The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 Pisa, Italy, May 12-17, 2013
Note

QC 20150114

Available from: 2013-06-14 Created: 2013-06-14 Last updated: 2015-01-14Bibliographically approved

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Thakre, Sachin

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