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The low carbon 46Ni-35Cr-9Mo alloy is a solid solution strengthened cast Ni-Cr-Mo alloy additionally containing Cu and N. This work reports on the properties achievable for a centrifugally cast low carbon 46Ni-35Cr-9Mo alloy tube of 4500 mm length and 55 mm wall thickness.
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The work is mainly focused on the corrosion mechanism at low pH (>4) and the order of which the discontinuous and continuous intermetallic phases dissolve. Compositions of each phase, and the area ratio between intermetallic phases and the alpha matrix have been calculated as an average of 20 measurements.
Additive manufacturing (AM), commonly referred to as 3D printing, offers advantages over traditionalproduction methods, such as quick prototyping, short production runs and intricate, thin section,microfluidic, variable composition, and low-waste designs. These exciting features are accompanied bynew challenges, such as higher costs, the possibility of variable quality, and inherently anisotropicproperties.
Existing AM technologies include 3D printing, rapid prototyping (RP), direct digital manufacturing (DDM),selective laser melting (SLM), and direct metal laser Sintering (DMLS).
Nuclear energy currently contributes approximately 10 % of the worldwide energy mix.1 Nuclear energy generation is a form of low-carbon electricity, typically run as base-load, which alongside renewables can help nations toward climate change goals. Nuclear fission thermal reactors make up the majority of the reactors operating today. Nuclear fusion on the other hand is a promising alternative which produces less radioactive waste and does not have a reliance on the finite source of uranium fuel. Eurofer-97, a reduced activation ferritic-martensitic (RAFM) steel, will be used as a structural material for fusion reactors. The earliest literature reference to RAFM steels originated from 1994 by Abe et al.2 One option for the European demonstration fusion reactor (DEMO) is to use a water-cooled lead-lithium (PbLi) breeder blanket (WCLL BB) design for heat extraction. Breeder blankets will be used to generate a source of tritium, for the fusion reaction with deuterium.
A major fire in a Reactor Effluent Air Cooler (REAC) of the Hydrocracker Unit (HCU). Visual inspection was made on the failed portion. Metallurgical investigation, macrostructural and microstructural analysis, Scanning Electron Microscopy, and Energy Dispersive x-ray Spectroscopy was conducted on the failed air cooler.
During plant shutdown maintenance, some components cannot be removed out of service immediately for metallurgical examination due to high cost involved and loss of production hours. The best alternative is to replicate the lab based metallography work under the field conditions. Field Metallography and Replication (FMR) also known as in-situ metallography is a powerful non-destructive test (NDT) tool used to examine the microstructure of the component when it is still in service. Moreover, FMR is also used to study the microstructural alterations for the fitness for service assessment.
This paper provides case studies of materials in Natural Gas Processing facility where FMR was used as an NDT tool without sectioning the component. This paper discusses the damage mechanisms such as sigma phase embrittlement, stress relaxation cracking and creep.
The harsh environment such as elevated temperature, radiation, elevated pressure, and potentially corrosive in nuclear reactors compromises material performance. Over time, repair and/or replacement through welding is needed for damaged parts and components. Thus, repair welding is essential to ensure the long-term viability, competitiveness, and safe lifetime extensions of the existing US reactor fleet.