AbstractStrain gages are applied to get the strain and stress of a CPR1000 Nuclear Power Plant (NPP) pressurizer during the pre-delivery hydrostatic test. The measured strain curves are discussed to find the deformation features of the cylinder. The stresses of cylindrical base metal, longitudinal welds and girth welds are calculated and compared with the theoretical values. The stresses in girth welds and upper head nozzle welds show non-uniformity at these areas. The possible reasons are discussed for this phenomenon. The stress intensity is calculated and evaluated according to the allowable limit. The fatigue usage factor is evaluated by considering the effect of internal pressure rise-and-fall cycle to pressurizer’s total fatigue life....
AbstractThe paper discusses the issue of the modelling of strains and stresses resulting from heatin...
A pressure vessel typically consists of large cylindrical and / or spherical containers with nozzles...
This report describes mechanical analyses of cylindrical part of the VVER 440-, BWR- and EPR-type ca...
The PV-4 isostatic press has a very large working volume (98 ft{sup 3}) that was designed for routin...
In nuclear power plant, anchor bolts for pressurizer supports are sufficiently used in terms of safe...
When the material yields local stress and strain behaviour changes, especially if there is a notch, ...
AbstractIn-situ Property Measurement System based on ball indentation technique has been developed f...
Since about a decade an important issue appeared in nuclear technology and in nuclear reactor safety...
THE WORK DEALS WITH THE STRESS AND FRACTURE MECHANICS ANALYSIS, AS APPLIED FOR THE SAFE...
The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combin...
Alloy 600 penetrations in several pressurized water reactors have experienced primary water stress c...
In the present article the stress-strain state of the lower traverse of the central ejector of the h...
This report is concerned with the analysis and its' review of a prestresied concrete reactor vessel ...
Abstract Residual stresses are present in materials or structural component in the absence of extern...
A hydro-pneumatic machine for performing material tests at intermediate strain-rates is described, a...
AbstractThe paper discusses the issue of the modelling of strains and stresses resulting from heatin...
A pressure vessel typically consists of large cylindrical and / or spherical containers with nozzles...
This report describes mechanical analyses of cylindrical part of the VVER 440-, BWR- and EPR-type ca...
The PV-4 isostatic press has a very large working volume (98 ft{sup 3}) that was designed for routin...
In nuclear power plant, anchor bolts for pressurizer supports are sufficiently used in terms of safe...
When the material yields local stress and strain behaviour changes, especially if there is a notch, ...
AbstractIn-situ Property Measurement System based on ball indentation technique has been developed f...
Since about a decade an important issue appeared in nuclear technology and in nuclear reactor safety...
THE WORK DEALS WITH THE STRESS AND FRACTURE MECHANICS ANALYSIS, AS APPLIED FOR THE SAFE...
The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combin...
Alloy 600 penetrations in several pressurized water reactors have experienced primary water stress c...
In the present article the stress-strain state of the lower traverse of the central ejector of the h...
This report is concerned with the analysis and its' review of a prestresied concrete reactor vessel ...
Abstract Residual stresses are present in materials or structural component in the absence of extern...
A hydro-pneumatic machine for performing material tests at intermediate strain-rates is described, a...
AbstractThe paper discusses the issue of the modelling of strains and stresses resulting from heatin...
A pressure vessel typically consists of large cylindrical and / or spherical containers with nozzles...
This report describes mechanical analyses of cylindrical part of the VVER 440-, BWR- and EPR-type ca...