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Creep-fatigue evaluation of normalized and tempered modified 9Cr-1Mo

Author
AOTO, K; KOMINE, R; UENO, F; KAWASAKI, H; WADA, Y
Power reactor and Nuclear Fuel Development Corp., Oarai eng. cent., materials development sect., Higashi-Ibaraki-gun, Ibaraki 311-13, Japan
Source

Nuclear engineering and design. 1994, Vol 153, Num 1, pp 97-110 ; ref : 21 ref

CODEN
NEDEAU
ISSN
0029-5493
Scientific domain
Energy; Metallurgy, welding
Publisher
Elsevier, Amsterdam
Publication country
Netherlands
Document type
Article
Language
English
Keyword (fr)
Acier ferritique Ductilité Durée vie Fatigue oligocyclique Fatigue Fluage Générateur vapeur Mécanisme action Propagation fissure Propriété mécanique Revenu Réacteur nucléaire Réacteur rapide Résistance mécanique Surgénérateur
Keyword (en)
Ferritic steel Ductility Lifetime Low cycle fatigue Fatigue Creep Steam generator Mechanism of action Crack propagation Mechanical properties Tempering Nuclear reactor Fast reactor Strength Breeder
Keyword (es)
Acero ferrítico Ductilidad Tiempo vida Fatiga oligocíclica Fatiga Fluencia Generador vapor Mecanismo acción Propagación fisura Propiedad mecánica Revenido Reactor nuclear Reactor rápido Resistencia mecánica Reactor reproductor
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
3394510

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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