Materials Reliability Program: Environmental Fatigue Testing of Type 304L Stainless Steel U-bends in Simulated PWR Primary Water (MRP-100): Phase A (Optimization of Test Procedures and Baseline Testing)
Laboratory data generated over the past two decades indicate the possibility of a significant reduction in component fatigue life when reactor water environmental effects are experimentally simulated. However, these laboratory data have not been confirmed by nuclear power plant component operating experience. In a recent comprehensive review of laboratory, component and structural test data performed through the EPRI Materials Reliability Program flow rate was identified as a critical variable that was generally not considered in laboratory studies but is applicable in plant operating environments. Available corrosion fatique data for carbon/low-alloy steel piping components suggest that high flow is beneficial regarding the effects of reactor water environments. Similar information is lacking for stainless steel piping materials. MRP-49 recommended that additional laboratory testing be done.
- Research Organization:
- Electric Power Research Institute
- Sponsoring Organization:
- USDOE-Office of Nuclear Energy, Science and Technology (NE)
- DOE Contract Number:
- FC07-03ID14536
- OSTI ID:
- 862425
- Report Number(s):
- 1007853
- Country of Publication:
- United States
- Language:
- English
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