[[abstract]]An analysis based on available materials property data has been performed to compare the inelastic response of first-wall structural materials. The first wall is assumed to be operated under the conditions of the pulse surface heat load, coolant pressure, and bombardment from energetic particles. An axisymmetric inelastic stress analysis calculates the long-term redistribution of the stress in a thin-walled plate element of a cylindrical module that is subjected to membrane load. The plate is free to expand but is constrained from bending. The redistribution is caused by inelastic deformation from irradiation creep and swelling. The present effort has concentrated on the performance of two candidate structural materials, namely,...
For the future fusion demonstration power plant, DEMO, several blanket designs are currently under c...
Cover plates are used in current designs for high temperature gas-cooled reactors to compress the mi...
Materials for the application in the first wall of fusion reactors of the Tokamak type are subjected...
[[abstract]]The severe effects of radiation damage and the poor thermal conductivity of type 316 sta...
[[abstract]]Several structural materials, including Type 316 stainless steel, Fe-Cr martensitic stee...
The impact of swelling in 20% cold-worked Type 316 stainless steel on first wall lifetime is assesse...
It is widely anticipated that one formulation of ferritic steel, HT9, will be utilized in the fabric...
Methods of analysis for fusion first wall design are developed. Several design lim-its have been eva...
Next-generation advanced reactor system designs present new challenges for material design and selec...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Abstract. The development of First Wall and Blanket materials which are capable of withstanding many...
A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall load...
This work deals with the design of a fusion reactor first-wall material, taking into account both lo...
2.00LD:9091.9F(CLM-R--217). / BLDSC - British Library Document Supply CentreSIGLEGBUnited Kingdo
Experimental thermal-creep strain data for modified 9Cr1Mo steel have been analyzed using an number ...
For the future fusion demonstration power plant, DEMO, several blanket designs are currently under c...
Cover plates are used in current designs for high temperature gas-cooled reactors to compress the mi...
Materials for the application in the first wall of fusion reactors of the Tokamak type are subjected...
[[abstract]]The severe effects of radiation damage and the poor thermal conductivity of type 316 sta...
[[abstract]]Several structural materials, including Type 316 stainless steel, Fe-Cr martensitic stee...
The impact of swelling in 20% cold-worked Type 316 stainless steel on first wall lifetime is assesse...
It is widely anticipated that one formulation of ferritic steel, HT9, will be utilized in the fabric...
Methods of analysis for fusion first wall design are developed. Several design lim-its have been eva...
Next-generation advanced reactor system designs present new challenges for material design and selec...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Abstract. The development of First Wall and Blanket materials which are capable of withstanding many...
A generalized model of a first wall made of 20% cold-worked steel was examined for neutron wall load...
This work deals with the design of a fusion reactor first-wall material, taking into account both lo...
2.00LD:9091.9F(CLM-R--217). / BLDSC - British Library Document Supply CentreSIGLEGBUnited Kingdo
Experimental thermal-creep strain data for modified 9Cr1Mo steel have been analyzed using an number ...
For the future fusion demonstration power plant, DEMO, several blanket designs are currently under c...
Cover plates are used in current designs for high temperature gas-cooled reactors to compress the mi...
Materials for the application in the first wall of fusion reactors of the Tokamak type are subjected...