After the Fukushima Daiichi nuclear power plant accident due to the pacific coast of Tohoku earthquake and Tsunami, we have been developing an analysis method considering creep damage mechanisms based on three-dimensional analysis in order to estimate condition of the fuel debris and failure behavior of the reactor due to severe accidents for the early completion of the decommissioning of nuclear power plants. We have also been obtaining material properties that are not provided in existing databases or literature for the analysis. In this study, we measure the tensile and creep properties of low alloy steel, Ni-based alloy, and stainless steel at high temperatures near the melting points. Using experimental data, some parameters for the cr...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Two different topics of Grade 91 steel are investigated for Gen IV nuclear reactor pressure vessel a...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
AbstractTime-dependent loads may significantly affect on structural integrity of RPV (Reactor Pressu...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
In this study, the Liu–Murakami (LM) creep damage-coupled model was considered to evaluate the creep...
This study aims to investigate buckling behaviors of a slender stainless steel column under compress...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
Structural integrity of power plant component is usually estimate by its residual service life. Inpu...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
Using stress rupture results openly available for Grade 91 steel, three features of a new methodolog...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Two different topics of Grade 91 steel are investigated for Gen IV nuclear reactor pressure vessel a...
In existing severe accident codes such as MELCOR and THALES2, rupture of reactor pressure vessel (RP...
AbstractTime-dependent loads may significantly affect on structural integrity of RPV (Reactor Pressu...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible fail...
A severe accident in a nuclear power plant could result in the relocation of large quantities of mol...
The creep-rupture behaviour of a Type DIN 1.4970 austenitic stainless steel has been investigated at...
In this study, the Liu–Murakami (LM) creep damage-coupled model was considered to evaluate the creep...
This study aims to investigate buckling behaviors of a slender stainless steel column under compress...
International audienceIn the event of a severe core meltdown accident in a pressurised water reactor...
Structural integrity of power plant component is usually estimate by its residual service life. Inpu...
International audienceIn the event of a severe core meltdown accident in a pressurized water reactor...
Using stress rupture results openly available for Grade 91 steel, three features of a new methodolog...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
A new approach to thermal creep deformation analysis, termed the θ-projection concept, is applied to...
Two different topics of Grade 91 steel are investigated for Gen IV nuclear reactor pressure vessel a...