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The LIVE program - Results of test L1 and joint analyses on transient molten pool thermal hydraulics

Author
BUCK, M1 ; BURGER, M1 ; MIASSOEDOV, A2 ; GAUS-LIU, X2 ; PALAGIN, A2 ; GODIN-JACQMIN, L3 ; TRAN, C. T4 ; MA, W. M4 ; CHUDANOV, V5
[1] Institut für Kemenergetik und Energiesysteme, Universität Stuttgart, Pfaffenwaldring 31, 70569 Stuttgart, Germany
[2] IRSN Forschungzentrum Karlsruhe (FZK) GmbH, Postfach 3640, 76021 Karlsruhe, Germany
[3] Commissariat à l'Energie Atomique (CEA), DEN/STRI/LMA, Cadarache, 13115 St-Paul-lez-Durance, France
[4] Kungl Tekniska Högskolan (KTH), AlbaNova University Center, Roslagstullbacken 21, 10691 Stockholm, Sweden
[5] Nuclear Safety Institute, 52, B. Tulskaya, 113191 Moscow, Russian Federation
Conference title
Major achievements after 4,5 years of SARNET Severe Accident Research Network of Excellence (6th European Reserach Framework Programme)
Conference name
European Review Meeting on Severe Accident Research (ERMSAR) (ERMSAR) (Nesseber 2008-09-23)
Author (monograph)
BAL RAJ SEHGAL (Editor)1 ; VAN DORSSELAERE, Jean-Pierre (Editor)2 ; ALBIOL, Thierry (Editor)2 ; JACQUEMAIN, Didier (Editor); JOURNEAU, Christophe (Editor)3
[1] Kungl Tekniska Högskolan (KTH), AlbaNova University Center, Schwertnergrasse 1, 50667 Köln, Germany
[2] Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3, 13115 St-Paul-Lez-Durance, France
[3] Commissariat à l'Energie Atomique (CEA), DEN/STRI/LMA, Cadarache, 13115 St-Paul-Lez-Durance, France
Source

Progress in nuclear energy (New series). 2010, Vol 52, Num 1, pp 46-60, 15 p ; ref : 1/2 p

ISSN
0149-1970
Scientific domain
Energy
Publisher
Elsevier, Kidlington
Publication country
United Kingdom
Document type
Conference Paper
Language
Russian
Author keyword
In-vessel retention Molten pool Severe accidents
Keyword (fr)
Accident Code calcul Coeur réacteur Essai sur modèle Etude comparative Faisabilité Fusion coeur réacteur Incertitude Modélisation Mécanique fluide numérique Noyage Réacteur nucléaire Régime permanent Régime transitoire Sécurité réacteur fission Sûreté nucléaire Thermohydraulique
Keyword (en)
Accident Computation code Reactor core Model test Comparative study Feasibility Meltdown Uncertainty Modeling Computational fluid dynamics Flooding Nuclear reactor Steady state Unsteady state Fission reactor safety Nuclear safety Thermohydraulics
Keyword (es)
Accidente Código computación Núcleo reactor Ensayo sobre modelo Estudio comparativo Practicabilidad Incertidumbre Modelización Mecánica fluido numérica Inundación Reactor nuclear Régimen permanente Régimen transitorio Seguridad nuclear Termohidraúlica
Classification
Pascal
001 Exact sciences and technology / 001D Applied sciences / 001D06 Energy / 001D06D Energy. Thermal use of fuels / 001D06D04 Installations for energy generation and conversion: thermal and electrical energy. / 001D06D04D Fission nuclear power plants

Discipline
Energy
Origin
Inist-CNRS
Database
PASCAL
INIST identifier
22331324

Sauf mention contraire ci-dessus, le contenu de cette notice bibliographique peut être utilisé dans le cadre d’une licence CC BY 4.0 Inist-CNRS / Unless otherwise stated above, the content of this bibliographic record may be used under a CC BY 4.0 licence by Inist-CNRS / A menos que se haya señalado antes, el contenido de este registro bibliográfico puede ser utilizado al amparo de una licencia CC BY 4.0 Inist-CNRS

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