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51316-7237-Corrosion Assessment of Nickel-based Alloy Candidates for SCWR Fuel Cladding

Picture for Corrosion Assessment of Nickel-based Alloy Candidates for SCWR Fuel Cladding
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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.

Product Number: 51316-7237-SG
ISBN: 7237 2016 CP
Author: Yimin Zeng
Publication Date: 2016
Industries: Energy Generation , Materials Selection and Design
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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

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

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ISBN: 7223 2016 CP
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