This is the seventh progress report of the U.S. Nuclear Regulatory Commission`s research program entitled {open_quotes}Short Cracks in Piping and Piping Welds{close_quotes}. The program objective is to verify and improve fracture analyses for circumferentially cracked large-diameter nuclear piping with crack sizes typically used in leak-before-break (LBB) analyses and in-service flaw evaluations. All work in the eight technical tasks have been completed. Ten topical reports are scheduled to be published. Progress only during the reporting period, March 1993 - December 1994, not covered in the topical reports is presented in this report. Details about the following efforts are covered in this report: (1) Improvements to the two computer prog...
This report presents a summary of the results from three one-day international round-robin workshops...
This report presents the results of the material property evaluation efforts performed within Task 3...
The observation of numerous small and large cracks in ferritic feed water pipes of boiling (BWR) and...
Leak-before-break (LBB) analyses for circumferentially cracked pipes are currently being conducted i...
This report presents the results from Task 1 of the Second International Piping Integrity Research G...
The IPIRG-2 program was an international group program managed by the US NRC and funded by organizat...
Leaks and cracks in the heat-affected zones of weldments in austenitic stainless steel piping and as...
This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The I...
Three-dimensional, nonlinear finite element analyses were performed for three sizes of circumferenti...
· 16.. Abstract (Limit: 200 words) Three-dimensional, nonlinear finite element analyses were perform...
Pipes are classified as one of the safest and convenient mode of transportation for flammable liquid...
This paper describes a fracture assessment method for a pipe having multiple circumferential flaws. ...
"Date published: June 1979."Prepared for Office of Nuclear Reactor Regulation, U.S. Nuclear Regulato...
This report is an in-depth summary of the state-of-the-art in nuclear piping fracture mechanics. It ...
Traditional flaw evaluation in the nuclear field uses conservative methods to predict maximum load c...
This report presents a summary of the results from three one-day international round-robin workshops...
This report presents the results of the material property evaluation efforts performed within Task 3...
The observation of numerous small and large cracks in ferritic feed water pipes of boiling (BWR) and...
Leak-before-break (LBB) analyses for circumferentially cracked pipes are currently being conducted i...
This report presents the results from Task 1 of the Second International Piping Integrity Research G...
The IPIRG-2 program was an international group program managed by the US NRC and funded by organizat...
Leaks and cracks in the heat-affected zones of weldments in austenitic stainless steel piping and as...
This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The I...
Three-dimensional, nonlinear finite element analyses were performed for three sizes of circumferenti...
· 16.. Abstract (Limit: 200 words) Three-dimensional, nonlinear finite element analyses were perform...
Pipes are classified as one of the safest and convenient mode of transportation for flammable liquid...
This paper describes a fracture assessment method for a pipe having multiple circumferential flaws. ...
"Date published: June 1979."Prepared for Office of Nuclear Reactor Regulation, U.S. Nuclear Regulato...
This report is an in-depth summary of the state-of-the-art in nuclear piping fracture mechanics. It ...
Traditional flaw evaluation in the nuclear field uses conservative methods to predict maximum load c...
This report presents a summary of the results from three one-day international round-robin workshops...
This report presents the results of the material property evaluation efforts performed within Task 3...
The observation of numerous small and large cracks in ferritic feed water pipes of boiling (BWR) and...