skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Analysis of experiments on stainless steel flux welds

Technical Report ·
OSTI ID:6561738

This report describes experimental and analytical efforts to evaluate fracture of stainless steel flux-welded pipe. Seven pipe fracture experiments (four with through-wall circumferential cracks and three with circumferential internal surface cracks) were conducted at 550/sup 0/F (288/sup 0/C). Material characterization efforts involved laboratory specimen tests to assess specimen size effects, effects of solution-annealing, and crack-growth behavior in the HAZ, along the fusion line, and in the weld metal. Efforts involved assessing the net-section-collapse analysis, the plastic-zone screening criterion, inherent safety margins in the IWB-3640 flux weld analysis, through-wall-cracked pipe predictive J-estimation schemes for LBB analyses, eta-factor J-R curves calculated from the pipe experiments for comparison to C(T) specimen results, and finite element analysis of C(T) specimens and one pipe experiment. This report also evaluates the technical significance of these results and their significance relative to licensing decisions.

Research Organization:
Battelle Columbus Div., OH (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering Safety
OSTI ID:
6561738
Report Number(s):
NUREG/CR-4878; BMI-2151; ON: TI87900672
Country of Publication:
United States
Language:
English