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Supercritical water-cooled reactor (SCWR) is an innovative Generation IV nuclear reactor. Nickel-based alloys, such as UNS N06625, UNS R20033 and UNS N07214 alloys, are selected for the fuel cladding. Knowledge gaps exist as regards their use for the fuel cladding in the SCWR. This paper introduces laboratory results on corrosion and stress corrosion cracking (SCC) of the nickel-based alloys.
Supercritical water-cooled reactor (SCWR) is one of six innovative Generation IV reactor concepts and merits further research and development with the intent of being pursued for implementation in the next 30 years. According to the knowledge and experience obtained from existing nuclear reactor and other high temperature systems candidate materials that will be used for fabricating SCWR core components such as calandria pressure tube and hot/cold let piping etc. have been reasonably identified and selected. To achieve optimum thermal efficiency however the Canadian SCWR concept requires a fuel core outlet temperature of 650 °C at 25 MPa with fuel cladding operating temperature possibly up to 850 °C leading to the most challenging aspect of this novel reactor concept. A number of studies and investigations have been performed in the past years and several top-ranking candidate materials including austenitic stainless steels and nickel-based alloys have been pre-selected based on available public information. To determine which alloy is suitable for the SCWR applications there are still a number of questions needed to be clarified. In this paper the corrosion mechanism of Ni-based alloy under SCWR condition is reviewed. Our most recent laboratory results on corrosion and stress corrosion cracking resistance of the alloys are also present and discussed.
Key Word: Downloadable, Supercritical Water, Corrosion, SCC, nickel-based alloys
Carbon Capture and Storage (CCS). The CO2 stream, captured from power plants contains highly corrosive impurities including H2O vapor, oxygen, and hydrogen sulfide. This paper presents our study on corrosion of pipeline steel in sc-CO2 containing H2O, H2S and/or O2 impurities in an autoclave.
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This paper will provide an overview of activities related to the nondestructive examination of dry storage casks for spent nuclear fuel. The aim is to help ensure their integrity over extended interim storage periods.
Discussion on Transmission and Distribution (T&D) structures and system-wide cathodic protection as a mitigation technique. In general soil, corrosivity, lack of cathodic protection/coating, stray current AC interference and copper grounding should be considered in design of T&D structures.