Materials Reliability Program: Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water (MRP-188)
Technical Report
·
OSTI ID:878895
- Electric Power Research Institute
Laboratory data generated in the past decade indicate a significant reduction in component fatigue life when reactor water environmental effects are experimentally simulated. However, these laboratory data have not been supported by nuclear power plant component operating experience. In an earlier comprehensive review of laboratory component and structural test data performed through the EPRI Materials Reliability Program (MRP), flow rate was identified as a critical variable that was generally not considered in laboratory studies but applicable in plant operating environments. Available data for carbon/low-alloy steel piping components suggest that high flow is beneficial regarding the effects of a reactor water environment. Similar information is lacking for stainless steel piping materials. This report documents final results of an extensive testing program carried out to evaluate effects of flow rate on corrosion fatigue of small-scale, stainless steel components (U-bends) under simulated pressurized water reactor (PWR) primary water environmental conditions. No life-time-increasing effect of higher flow rate was observed, nor is higher flow expected to be detrimental.
- Research Organization:
- Electric Power Research Institute
- Sponsoring Organization:
- USDOE - Office of Nuclear Energy, Science and Technology (NE)
- DOE Contract Number:
- FC07-03ID14536
- OSTI ID:
- 878895
- Report Number(s):
- 1013028
- Country of Publication:
- United States
- Language:
- English
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