To study irradiation creep at 400{degrees}C and below, a series of six austenitic stainless steels and two ferritic alloys was irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He production rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor; and, after an atomic displacement level of 7.4 dpa, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation temperatures of 60, 200, 330, and 400{degrees}C were studied with internally pressurized tubes of type 316 stainless steel, PCA, HT 9, and a series of four laboratory heats of: Fe-13.5Cr-15Ni, Fe-13.5Cr-35Ni, Fe-1 3.5Cr-1 W-0.18Ti, and Fe-16Cr. At 330{de...
A novel capsule design has been developed for measurement of irradiation creep in pressurized tubes ...
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
International audienceSolution annealed 304L (SA 304L) and cold work 316 (CW 316) austenitic stainle...
tubes, creep modulus. Abstract: The report describes the historical aspects held in JSC "SSC-NI...
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...
A study of irradiation creep in vanadium-base alloys is underway with experiments in the Advanced Te...
International audienceCompared to austenitic stainless steels, largely employed in the early fission...
Many R&D programs are being conducted worldwide to study and, in some cases, develop materials with ...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
In-reactor tests designed to provide information on the relationship between compositional variation...
Materials deform faster under stress in the presence of irradiation by a process known as irradiatio...
Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport ...
A novel capsule design has been developed for measurement of irradiation creep in pressurized tubes ...
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...
International audienceSolution annealed 304L (SA 304L) and cold work 316 (CW 316) austenitic stainle...
tubes, creep modulus. Abstract: The report describes the historical aspects held in JSC "SSC-NI...
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...
A study of irradiation creep in vanadium-base alloys is underway with experiments in the Advanced Te...
International audienceCompared to austenitic stainless steels, largely employed in the early fission...
Many R&D programs are being conducted worldwide to study and, in some cases, develop materials with ...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
A series of model alloys are studied to understand irradiation embrittlement phenomena and similitud...
In-reactor tests designed to provide information on the relationship between compositional variation...
Materials deform faster under stress in the presence of irradiation by a process known as irradiatio...
Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport ...
A novel capsule design has been developed for measurement of irradiation creep in pressurized tubes ...
The effects of neutron irradiation on the steel reactor vessel for the modular high-temperature gas-...
International audienceIn PWR's, internals made of austenitic stainless steels (Cold Worked (CW) 316 ...