A5028336543- Nuclear Materials and Properties
- High-Temperature Coating Behaviors
- Fusion materials and technologies
- Aluminum Alloy Microstructure Properties
- Additive Manufacturing Materials and Processes
- Additive Manufacturing and 3D Printing Technologies
- Electrodeposition and Electroless Coatings
- Metallurgical Processes and Thermodynamics
- High Temperature Alloys and Creep
- Nuclear reactor physics and engineering
- Semiconductor materials and devices
- Metal Alloys Wear and Properties
- Semiconductor materials and interfaces
- Welding Techniques and Residual Stresses
- Metallurgy and Material Science
- Nanoporous metals and alloys
- Corrosion Behavior and Inhibition
General Electric (United States)
2023-2024
Georgia Institute of Technology
2021-2023
FeCrAl alloys are being investigated as candidate materials for light water reactor fuel claddings. The chemical composition of determines its resistance to corrosion under normal operating conditions. purpose this paper is investigate the effect 0, 1, 3 wt% Ni addition on passivation characteristics Fe17Cr5.5Al in oxygenated and hydrogenated simulated waters 3-month immersion. Current results show that improves condition decreases mass loss
Accident tolerant cladding materials should have improved properties under the LOCA conditions. FeCrAl alloys are promising with high-temperature steam oxidation resistance. Little efforts been put into understanding compositional effects on performance of at operating This work focuses effect Al concentration in three Fe-17Cr-xAl resistance 400 °C environment. study shows that increased reduces total oxide thickness, enhances formation a uniform Cr-oxide layer. and sufficient allows for...
FeCrAl alloys are promising candidates for next generation nuclear fuel cladding applications due to their high resistance hydrothermal corrosion, temperature steam oxidation, fretting, and creep properties. However, a potential area of concern is the precipitation Cr-enriched α’ phase which could have an implication on mechanical, oxidative degradation as well electrochemical behavior. Studies in this limited since most past been temperatures above miscibility gap. In work, we investigate...
Given the focus on developing novel accident-tolerant materials for nuclear fuel cladding applications, FeCrAl alloys have been considered as one of promising candidates. To optimize composition alloys, systematic studies are necessary to understand elemental effect oxidation behavior at normal and accident conditions. This work focuses understanding how presence 3 wt.% 8 Al in a Fe-21Cr alloy affects their steam mechanisms oxide architecture environment 400°C 1200°C. Results show that...
Fuel Cladding Materials for nuclear reactors need to have great fretting resistance, good mechanical properties under irradiation and corrosion/oxidation resistance. Since the Nuclear Reactor Failure at Fukushima, concerted efforts been taken develop novel materials with improved resistance towards degradation Loss of Coolant Accident Conditions (LOCA). FeCrAl-based alloys are promising given their high-temperature steam oxidation LOCA conditions. However, little put into understanding...
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FeCrAl alloys are being investigated as candidate materials for light water reactor fuel claddings. The chemical composition of determines their resistance to corrosion under normal operation conditions. purpose this paper is investigate the effect 0, 1, 3 wt% Ni addition on passivation characteristics Fe17Cr5.5Al in oxygenated and hydrogenated simulated waters 3-month immersion. Current results show that improves condition decreases mass loss condition.
The effect of 0, 1, 3 wt% Mo addition on the corrosion behavior Fe21Cr5.5Al was studied through steam tests at 400 °C and 1200 for first time. At °C, leads to porous oxide growth surface, compromising Cr subsequent Al2O3 layers development as Mo-free specimen. drastic evaporation promotes complete spallation surface scale. Current results show that sole is detrimental resistance FeCrAl alloy under both operational accidental scenarios.
Al-Zn-Mg-Cu alloys of the 7xxx series have proven to be excellent candidates for aerospace, defense, and automotive industries due their high strength weight ratio, corrosion resistance, fatigue performance. For additively manufactured using laser powder bed fusion (LPBF), non-conventional microstructures formed as a result one or more factors like alloy modification, LPBF process, subsequent thermal treatments can lead change in behavior mechanisms. Using scanning vibrating electrode...
Fuel Cladding Materials for nuclear reactors need to have great fretting resistance, good mechanical properties under irradiation and corrosion/oxidation resistance. Since the Nuclear Reactor Failure at Fukushima, concerted efforts been taken develop novel materials with improved resistance towards degradation Loss of Coolant Accident Conditions (LOCA). FeCrAl-based alloys are promising given their high-temperature steam oxidation LOCA conditions. However, little put into understanding...
The benefits of additive manufacturing (AM) process combined with the high-strength, corrosion resistant and fracture toughness properties 7xxx series aluminum alloys make them promising candidates for aerospace defense industries. However, these undergo unconventional thermal cycles during like laser powder bed fusion (LPBF) as well post-processing treatments hot isostatic pressing, resulting in microstructures different from equivalent wrought alloys. In our work, we investigate how...
Electroless nickel immersion gold (ENIG) is a common surface finish for high-reliability microelectronics circuitry due to its good solderability, corrosion resistance, layer thickness uniformity and applicability fine pitch applications 1 . ENIG deposition multistep process in which 3 6 micron (118-236 μ-in) of electroless (i.e. Ni-P) deposited onto the substrate material (typically copper), followed by galvanic displacement reaction replacing Ni with 0.04 0.1 microns (1.6 4 (Au). Despite...