The impact of swelling in 20% cold-worked Type 316 stainless steel on first wall lifetime is assessed. Three separate predictive swelling correlations, two of which are empirically derived from available fission reactor data and one which is largely based upon a theoretical model, have been used. The swelling equations have been incorporated into a materials lifetime code that examines the temperature-stress-strain-radiation effects history of fusion components. The code has been applied to the INTOR, DEMO, and STARFIRE first wall designs
IT IS EXPECTED THAT DURING PLASMA DISRUPTIONS THE FIRST WALL OF A TOKAMAK REACTOR WILL BE EXPO...
The performance of materials in fusion reactor DEMO has long been recognized as fundamental issue af...
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are th...
A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall load...
[[abstract]]An analysis based on available materials property data has been performed to compare the...
[[abstract]]The severe effects of radiation damage and the poor thermal conductivity of type 316 sta...
Methods of analysis for fusion first wall design are developed. Several design lim-its have been eva...
In pressurized water reactors (PWRs), stainless steel components are irradiated at temperatures that...
Correlations developed for void swelling and irradiation creep often arise from two separate data ba...
As many pressurized water reactors (PWRs) age and life extension of the aged plants is considered, v...
Samples of cold-rolled Type 316 stainless steel were irradiated in EBR- II to a fluence of about 8 x...
Four possible candidate materials for fusion reactor first wall have been analysed. A finite element...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Vita.The results of a modeling study of the swelling, creep and embrittlement of niobium used as the...
The article presents the first data on EK-164ID steel swelling after operational irradiation in a fa...
IT IS EXPECTED THAT DURING PLASMA DISRUPTIONS THE FIRST WALL OF A TOKAMAK REACTOR WILL BE EXPO...
The performance of materials in fusion reactor DEMO has long been recognized as fundamental issue af...
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are th...
A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall load...
[[abstract]]An analysis based on available materials property data has been performed to compare the...
[[abstract]]The severe effects of radiation damage and the poor thermal conductivity of type 316 sta...
Methods of analysis for fusion first wall design are developed. Several design lim-its have been eva...
In pressurized water reactors (PWRs), stainless steel components are irradiated at temperatures that...
Correlations developed for void swelling and irradiation creep often arise from two separate data ba...
As many pressurized water reactors (PWRs) age and life extension of the aged plants is considered, v...
Samples of cold-rolled Type 316 stainless steel were irradiated in EBR- II to a fluence of about 8 x...
Four possible candidate materials for fusion reactor first wall have been analysed. A finite element...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Vita.The results of a modeling study of the swelling, creep and embrittlement of niobium used as the...
The article presents the first data on EK-164ID steel swelling after operational irradiation in a fa...
IT IS EXPECTED THAT DURING PLASMA DISRUPTIONS THE FIRST WALL OF A TOKAMAK REACTOR WILL BE EXPO...
The performance of materials in fusion reactor DEMO has long been recognized as fundamental issue af...
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are th...