In this study, we evaluated the oxidation resistance of two Fe-Ni-Cr based alloys (stainless steel 316L and incoloy 800H/HT) in air and supercritical water at 600 ºC. Results indicate that Incoloy 800H/HT shows considerably better oxidation resistance in supercritical water, compared to stainless steel 316L, and therefore it is a better candidate as a structural material for SCWR. The difference in chemical composition of the alloys was found to be the main reason for better oxidation resistance of incoloy 800H/HT as it has higher amount of chromium and nickel and, on the contrary, lower amount of iron. This resulted in the formation of a protective layer on the surface which significantly retarded the oxidation in supercritical water envir...
Performance and efficiency of more advanced reactors like Super Critical Water Reactors (SCWRs) is l...
The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and ...
The Canadian Supercritical Water-cooled Reactors (SCWR), among the Generation IV (Gen IV) reactors c...
The goal of this paper is to determine the SCC susceptibility of candidate materials for SCWR incor...
The goal of this paper is to determine the SCC susceptibility of candidate materials for SCWR incore...
The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled...
The scope of this work was to characterize the corrosion resistance of candidate austenitic alloys i...
High temperature oxidation resistance is of critical importance for the in-reactor components of the...
Nuclear power systems have been under continuous development since the first nuclear power plant sta...
MCrAl (M Fe, Ni, or Co) alloys have exceptional corrosion and oxidation resistance and can be used a...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
The oxidation behavior of model binary and ternary alloys in supercritical water (SCW) was examined....
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation...
The advantage of using supercritical water (SCW) systems for power generation is based on the increa...
Performance and efficiency of more advanced reactors like Super Critical Water Reactors (SCWRs) is l...
The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and ...
The Canadian Supercritical Water-cooled Reactors (SCWR), among the Generation IV (Gen IV) reactors c...
The goal of this paper is to determine the SCC susceptibility of candidate materials for SCWR incor...
The goal of this paper is to determine the SCC susceptibility of candidate materials for SCWR incore...
The choice of materials is of great concern in the construction of Gen IV supercritical water-cooled...
The scope of this work was to characterize the corrosion resistance of candidate austenitic alloys i...
High temperature oxidation resistance is of critical importance for the in-reactor components of the...
Nuclear power systems have been under continuous development since the first nuclear power plant sta...
MCrAl (M Fe, Ni, or Co) alloys have exceptional corrosion and oxidation resistance and can be used a...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
The oxidation behavior of model binary and ternary alloys in supercritical water (SCW) was examined....
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation...
The advantage of using supercritical water (SCW) systems for power generation is based on the increa...
Performance and efficiency of more advanced reactors like Super Critical Water Reactors (SCWRs) is l...
The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and ...
The Canadian Supercritical Water-cooled Reactors (SCWR), among the Generation IV (Gen IV) reactors c...