International audienceOne of the main challenges for some reactors components in austenitic stainless steels at high temperature in-service conditions is the demonstration of their behavior up to 60 years. The creep lifetimes of these stainless steels require on the one hand to carry out very long term creep tests and on the other hand to understand and to model the damage mechanisms in order to propose physically-based predictions toward 60 years of service. Different batches of austenitic stainless steels like-type 316L with low carbon and closely specified nitrogen content, 316L(N), are subjected to numerous creep tests carried out at various stresses and temperatures between 525 °C and 700 °C up to nearly 50 • 103 h
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
AbstractDifferent batches of austenitic stainless steels (316LN) are subjected to numerous creep tes...
AbstractThe austenitic stainless steel 316 is of current interest as structural material for the fut...
The aim of this study is to investigate the creep test on static loading of stainless steelmaterials...
L’endommagement de fluage des aciers 316L(N) a été étudié expérimentalement et théoriquement à des t...
Designers of new power-generation plants are looking to make use of new and existing high-strength a...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
International audienceOne of the main challenges for some reactors components in austenitic stainles...
AbstractDifferent batches of austenitic stainless steels (316LN) are subjected to numerous creep tes...
AbstractThe austenitic stainless steel 316 is of current interest as structural material for the fut...
The aim of this study is to investigate the creep test on static loading of stainless steelmaterials...
L’endommagement de fluage des aciers 316L(N) a été étudié expérimentalement et théoriquement à des t...
Designers of new power-generation plants are looking to make use of new and existing high-strength a...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...