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)
Technical Report
·
OSTI ID:821421
- EPRI
OAK-B135 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 fatigue 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 performed to improve the applicability of laboratory test results under simulated reactor water environmental conditions for stainless steel materials. This report documents progress made in an extensive testing program underway to evaluate the effects of flow rate on fatigue of 304L stainless steel in simulated PWR primary water.
- Research Organization:
- EPRI (US)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
- DOE Contract Number:
- FC03-00NE22796
- OSTI ID:
- 821421
- Report Number(s):
- 1007853
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CORROSION FATIGUE
ENVIRONMENTAL EFFECTS
ENVIRONMENTAL FATIGUE
PIPING FLOW RATE
NUCLEAR POWER PLANT PIPING
STAINLESS STEEL PIPING (REPORT SUBMITTED ON CD ROM UNDER OSTI ID 821357) OK TO RELEASE
NO RESTRICTION ON COPYRIGHT
EPRI
FLOW RATE
NUCLEAR POWER PLANTS
OPTIMIZATION
RELIABILITY
STAINLESS STEELS
STEELS
TESTING
WATER
36 MATERIALS SCIENCE
CORROSION FATIGUE
ENVIRONMENTAL EFFECTS
ENVIRONMENTAL FATIGUE
PIPING FLOW RATE
NUCLEAR POWER PLANT PIPING
STAINLESS STEEL PIPING (REPORT SUBMITTED ON CD ROM UNDER OSTI ID 821357) OK TO RELEASE
NO RESTRICTION ON COPYRIGHT
EPRI
FLOW RATE
NUCLEAR POWER PLANTS
OPTIMIZATION
RELIABILITY
STAINLESS STEELS
STEELS
TESTING
WATER