International audienceA correlation is attempted between microstructural observations by various complementary techniques, which have been implemented within the PERFECT project and the hardening measured by tensile tests of reactor pressure vessel steel and model alloys after irradiation to a dose of ∼7 × 1019 n cm−2. This is done, using the simple hardening model embodied by the Orowan equation and applying the most suitable superposition law, as suggested by a parametric study using the DUPAIR line tension code. It is found that loops are very strong obstacles to dislocation motion, but due to their low concentration, they only play a minor role in the hardening itself. For the precipitates, the contrary is found, although they are quite...
A model for the development of microstructure during irradiation in fast reactors has been adapted f...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
As an important part of the design and development of advanced nuclear fission and fusion reactors, ...
International audienceA correlation is attempted between microstructural observations by various com...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
International audienceThe plastic behavior of irradiated Reactor Pressure Vessel (RPV) steels is des...
In this paper, we examine the post-yield true stress vs true strain behavior of irradiated pressure ...
Irradiation hardening is an issue of practical importance as it relates to the remanent life and the...
A large matrix of simple alloys and complex commercial type steels was irradiated over a range of fl...
International audienceThe context ofthis work is relative to the aging of vessel steels in pressuriz...
International audienceIrradiation creep was investigated in different austenitic steels. Pressurized...
The reactor pressure vessel steel of a nuclear power plant is subjected to fast neutron induced embr...
Reactor pressure vessel steel welds are affected by irradiation during operation. The irradiation re...
A model for the development of microstructure during irradiation in fast reactors has been adapted f...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
As an important part of the design and development of advanced nuclear fission and fusion reactors, ...
International audienceA correlation is attempted between microstructural observations by various com...
The possibility of extending the operational life of reactor pressure vessels (RPV) up to 80 years p...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
International audienceThe plastic behavior of irradiated Reactor Pressure Vessel (RPV) steels is des...
In this paper, we examine the post-yield true stress vs true strain behavior of irradiated pressure ...
Irradiation hardening is an issue of practical importance as it relates to the remanent life and the...
A large matrix of simple alloys and complex commercial type steels was irradiated over a range of fl...
International audienceThe context ofthis work is relative to the aging of vessel steels in pressuriz...
International audienceIrradiation creep was investigated in different austenitic steels. Pressurized...
The reactor pressure vessel steel of a nuclear power plant is subjected to fast neutron induced embr...
Reactor pressure vessel steel welds are affected by irradiation during operation. The irradiation re...
A model for the development of microstructure during irradiation in fast reactors has been adapted f...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
As an important part of the design and development of advanced nuclear fission and fusion reactors, ...