International audienceSolution annealed 304L (SA 304L) and cold work 316 (CW 316) austenitic stainless steel irradiation creep behaviour have been studied thoroughly. Irradiations were carried out in fast breeder reactors BOR-60 (at 330 degrees C, up to 120 dpa) and EBR-II (at 375 degrees C, up to 10.5 dpa), and in the OSIRIS mixed spectrum reactor (at 330 degrees C, up to 9.8 dpa). After an incubation threshold, the irradiation creep of the austenitic stainless steels is linear in stress and in dose. Creep appears to be athermal in this temperature range. A significant difference in the behaviour is measured between the creep of SA 304L and CW 316. In order to study the anisotropy of loop population, which would be the signature of a possi...
<div><p>Stainless steels are well known by their corrosion resistance. The austenitic types, in part...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
International audienceIon irradiations have been performed at 450 °C on 304 and 304L austenitic stai...
International audienceSolution annealed 304L (SA 304L) and cold work 316 (CW 316) austenitic stainle...
International audienceA cluster dynamic model has been adapted to test the Stress Induced Preferenti...
International audienceIrradiation creep was investigated in different austenitic steels. Pressurized...
To study irradiation creep at 400{degrees}C and below, a series of six austenitic stainless steels a...
International audienceASTRID is a fast-reactor prototype for the 4th generation of nuclear power pla...
SEcond editionInternational audienceA knowledge of the dimensional stability of reactor structural c...
In-reactor tests designed to provide information on the relationship between compositional variation...
tubes, creep modulus. Abstract: The report describes the historical aspects held in JSC "SSC-NI...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
International audiencePost-irradiation deformation behavior of solution-annealed (SA) and cold-worke...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
<div><p>Stainless steels are well known by their corrosion resistance. The austenitic types, in part...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
International audienceIon irradiations have been performed at 450 °C on 304 and 304L austenitic stai...
International audienceSolution annealed 304L (SA 304L) and cold work 316 (CW 316) austenitic stainle...
International audienceA cluster dynamic model has been adapted to test the Stress Induced Preferenti...
International audienceIrradiation creep was investigated in different austenitic steels. Pressurized...
To study irradiation creep at 400{degrees}C and below, a series of six austenitic stainless steels a...
International audienceASTRID is a fast-reactor prototype for the 4th generation of nuclear power pla...
SEcond editionInternational audienceA knowledge of the dimensional stability of reactor structural c...
In-reactor tests designed to provide information on the relationship between compositional variation...
tubes, creep modulus. Abstract: The report describes the historical aspects held in JSC "SSC-NI...
The currently operating Generation II Advanced Gas-Cooled Reactors (AGR) in the nuclear power statio...
International audiencePost-irradiation deformation behavior of solution-annealed (SA) and cold-worke...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
<div><p>Stainless steels are well known by their corrosion resistance. The austenitic types, in part...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
International audienceIon irradiations have been performed at 450 °C on 304 and 304L austenitic stai...