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Analysis of In-Vessel Coolability and Retention with Control Rod Guide Tube Cooling in Boiling Water Reactors
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
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
2009 (English)Conference paper, Published paper (Refereed)
Place, publisher, year, edition, pages
2009.
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-53641OAI: oai:DiVA.org:kth-53641DiVA: diva2:470517
Conference
NEA/SARNET2 Workshop - In-Vessel Coolability, NEA Headquarters, Issy-les-Moulineaux, France, October 12-14, 2009
Note
QC 20120110Available from: 2011-12-29 Created: 2011-12-29 Last updated: 2012-01-10Bibliographically approved

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Kudinov, Pavel

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CiteExportLink to record
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