AbstractDissimilar metal welded joints are used in primary water systems of pressurized water reactor in nuclear power plant. They are mainly used to connect the ferritic steel pipe-nozzles of the pressure vessels such as reactor pressure vessels, steam generators and pressurizers with the austenitic stainless steel safe end. Thus, maintaining integrity of such joints is critical to ensure their safe service. As local wall thinning may probably appear at safe end to due to erosion and corrosion, assessment methods with local wall thinning are urgently needed. In this paper, three-dimensional finite element analysis models with and without considering local wall thinning were built for dissimilar metal welded joints connected the safe end to...
After long-term service, metallic pipe components in nuclear power plant, chemical, petroleum indust...
Dissimilar metal welds are commonly found in the primary piping of pressurized water nuclear reactor...
A safety analysis for a nuclear reactor pressure vessel based on linear elastic fracture mechanics c...
Pressure vessel and piping systems are essential components of all power plants. After long-term ser...
A severe accident management concept, known as ‘in-vessel retention (IVR)’, is widely used in advanc...
Local wall thinning is a common defect on the surface of pipelines, which can cause damage to the pi...
In this paper, the authors apply the ASME Boiler & Pressure Vessel Code to the structural assessment...
When a flaw is detected in the stainless steel pipes at nuclear power plants during in-service inspe...
The use of finite element based limit load analysis for the assessment of the primary load capacity ...
AbstractBuckling collapse is one of the important failure modes of pressure vessel. But, in the past...
The presence of weld sinkage in cir-seam joint of pressure vessels (cylindrical and spherical) has b...
Because of the extensive requirements for computer resources to perform nonlinear parametric stress ...
The computer resources needed to perform nonlinear finite element analyses on the shell-flange fille...
If a thin-walled pipe loaded with internal pressure and axial tension allows the appearance of plast...
A simplified method is proposed to evaluate limit load at incipient plastic collapse for a pipe made...
After long-term service, metallic pipe components in nuclear power plant, chemical, petroleum indust...
Dissimilar metal welds are commonly found in the primary piping of pressurized water nuclear reactor...
A safety analysis for a nuclear reactor pressure vessel based on linear elastic fracture mechanics c...
Pressure vessel and piping systems are essential components of all power plants. After long-term ser...
A severe accident management concept, known as ‘in-vessel retention (IVR)’, is widely used in advanc...
Local wall thinning is a common defect on the surface of pipelines, which can cause damage to the pi...
In this paper, the authors apply the ASME Boiler & Pressure Vessel Code to the structural assessment...
When a flaw is detected in the stainless steel pipes at nuclear power plants during in-service inspe...
The use of finite element based limit load analysis for the assessment of the primary load capacity ...
AbstractBuckling collapse is one of the important failure modes of pressure vessel. But, in the past...
The presence of weld sinkage in cir-seam joint of pressure vessels (cylindrical and spherical) has b...
Because of the extensive requirements for computer resources to perform nonlinear parametric stress ...
The computer resources needed to perform nonlinear finite element analyses on the shell-flange fille...
If a thin-walled pipe loaded with internal pressure and axial tension allows the appearance of plast...
A simplified method is proposed to evaluate limit load at incipient plastic collapse for a pipe made...
After long-term service, metallic pipe components in nuclear power plant, chemical, petroleum indust...
Dissimilar metal welds are commonly found in the primary piping of pressurized water nuclear reactor...
A safety analysis for a nuclear reactor pressure vessel based on linear elastic fracture mechanics c...