A technology to determine shallow-flaw fracture toughness of reactor pressure vessel (RPV) steels is being developed for application to the safety assessment of RPVs containing postulated shallow surface flaws. Matrices of cruciform beam tests were developed to investigate and quantify the effects of temperature, biaxial loading, and specimen size on fracture initiation toughness of two-dimensional (constant depth), shallow surface flaws. The cruciform beam specimens were developed at Oak Ridge National Laboratory (ORNL) to introduce a prototypic, far-field. out-of-plane biaxial stress component in the test section that approximates the nonlinear stresses resulting from pressurized-thermal-shock or pressure-temperature loading of an RPV. Te...
The structural integrity of cracked mechanical components can be assessed using the fracture toughne...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
The brittle failure safety of reactor pressure vessels (RPV) has to be demonstrated for all load cas...
A technology to determine shallow-flaw fracture toughness of reactor pressure vessel (RPV) steels is...
Effects of biaxial loading on shallow-flaw fracture toughness were studied to determine potential im...
In structural integrity analysis of reactor pressure vessels (RPVs), a postulated shallow crack is...
Shallow-flaw fracture technology is being developed within the Heavy-Section Steel Technology (HSST)...
Shallow-flaw fracture technology is being developed for application to the safety assessment of radi...
Development continues on the technology used to assess the safety of irradiation-embrittled nuclear ...
A real crack to be assessed in a RPV is generally a shallow crack subjected to biaxial far-field str...
A testing program is described that utilizes full-thickness clad beam specimens to quantify fracture...
Fracture toughness assessments of nuclear pressure vessel (PV) steels are conducted on highly constr...
Biaxial loading exists in pressure vessel components in both U.S. Navy pressure vessels and in press...
The present study is concerned with an enhanced fracture mechanics characterization of engineering m...
In the paper, evaluation of 9 large scale experiments performed on uncladded cracked beams made of R...
The structural integrity of cracked mechanical components can be assessed using the fracture toughne...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
The brittle failure safety of reactor pressure vessels (RPV) has to be demonstrated for all load cas...
A technology to determine shallow-flaw fracture toughness of reactor pressure vessel (RPV) steels is...
Effects of biaxial loading on shallow-flaw fracture toughness were studied to determine potential im...
In structural integrity analysis of reactor pressure vessels (RPVs), a postulated shallow crack is...
Shallow-flaw fracture technology is being developed within the Heavy-Section Steel Technology (HSST)...
Shallow-flaw fracture technology is being developed for application to the safety assessment of radi...
Development continues on the technology used to assess the safety of irradiation-embrittled nuclear ...
A real crack to be assessed in a RPV is generally a shallow crack subjected to biaxial far-field str...
A testing program is described that utilizes full-thickness clad beam specimens to quantify fracture...
Fracture toughness assessments of nuclear pressure vessel (PV) steels are conducted on highly constr...
Biaxial loading exists in pressure vessel components in both U.S. Navy pressure vessels and in press...
The present study is concerned with an enhanced fracture mechanics characterization of engineering m...
In the paper, evaluation of 9 large scale experiments performed on uncladded cracked beams made of R...
The structural integrity of cracked mechanical components can be assessed using the fracture toughne...
This report discusses development on the technology used to assess the safety of irradiation-embritt...
The brittle failure safety of reactor pressure vessels (RPV) has to be demonstrated for all load cas...