THE CORROSION BEHAVIOR OF INCONEL NICKEL-CHROMIUM ALLOY AND NIOBIUM ALLOYS IN PRESSURIZED-WATER REACTOR ENVIROMENTS (in French)
Journal Article
·
· Energie Nucl.
OSTI ID:4698663
Corrosion experiments were conducted in simulated primary and secondary reactor waters on Inconel alloy specimens in several conditions of heat treatment and alloy compositions. Exposures to primary water were carried out under static conditions at 150, 288, and 360 c- C and under flowing reactor coolant conditions at 288 and 343 c- C. Stress specimens, weldments, and galvanic specimens were included in the study. Experiments on the corrosion behavior of niobium alloys were conducted in static 315 and 360 c- C water and in 400 c- C steam at 100 atm. Alloy compositions, exposure conditions, and results are given in tables. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- NSA Number:
- NSA-17-025735
- OSTI ID:
- 4698663
- Journal Information:
- Energie Nucl., Journal Name: Energie Nucl. Vol. Vol: 4
- Country of Publication:
- Country unknown/Code not available
- Language:
- French
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