Materials selection is one of the key tasks in Gen-IV reactor development. There is no known material that can meet the expected core outlet conditions of the Canadian SCWR concept (625{sup o}C core outlet temperature). High-Cr steels with excellent corrosion resistance are often susceptible to embrittlement due to the precipitation of sigma and other phases in the microstructure. Low-Cr steels such as P91 and oxide dispersion strengthened (ODS) steels exhibit good high-temperature mechanical properties, but the lack of sufficient Cr content makes this group alloy corrode too fast. Improvement in this alloy is needed in order for it to be considered as a piping construction material. In this report, the development of a metallic coating on ...
General corrosion tests and slow strain rate tensile tests (SSRT) were done on 9-20% Cr oxide disper...
AbstractThe corrosion behaviour of a ferritic/martensitic steel T91 and a martensitic stainless stee...
International audienceNi–Fe–Cr alloys are expected to be a candidate material for the generation IV ...
Materials selection is one of the key tasks in Gen-IV reactor development. There is no known materia...
The Canadian Generation-IV supercritical water reactor (SCWR) requires peak cladding surface tempera...
The materials selection for Gen IV supercritical water reactor in-core components faces major challe...
This paper summarizes the results of supercritical water corrosion studies of two ferritic oxide dis...
The scope of this work was to characterize the corrosion resistance of candidate austenitic alloys i...
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation...
Materials selection for Gen IV supercritical water reactor in-core components faces major challenges...
This work summarizes the results of corrosion studies of a surface treated austenitic stainless stee...
The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and ...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
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...
General corrosion tests and slow strain rate tensile tests (SSRT) were done on 9-20% Cr oxide disper...
AbstractThe corrosion behaviour of a ferritic/martensitic steel T91 and a martensitic stainless stee...
International audienceNi–Fe–Cr alloys are expected to be a candidate material for the generation IV ...
Materials selection is one of the key tasks in Gen-IV reactor development. There is no known materia...
The Canadian Generation-IV supercritical water reactor (SCWR) requires peak cladding surface tempera...
The materials selection for Gen IV supercritical water reactor in-core components faces major challe...
This paper summarizes the results of supercritical water corrosion studies of two ferritic oxide dis...
The scope of this work was to characterize the corrosion resistance of candidate austenitic alloys i...
The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation...
Materials selection for Gen IV supercritical water reactor in-core components faces major challenges...
This work summarizes the results of corrosion studies of a surface treated austenitic stainless stee...
The High Performance Light Water Reactor (HPLWR) is working at super-critical pressure (25 MPa) and ...
Concerns with greenhouse gas emissions and the uncertainty of long-term supply of fossil fuels have ...
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...
General corrosion tests and slow strain rate tensile tests (SSRT) were done on 9-20% Cr oxide disper...
AbstractThe corrosion behaviour of a ferritic/martensitic steel T91 and a martensitic stainless stee...
International audienceNi–Fe–Cr alloys are expected to be a candidate material for the generation IV ...