Abstract
The Canadian Generation-IV supercritical water reactor (SCWR) requires peak cladding surface temperature of 800˚C for a core outlet temperature of 625˚C. Materials selection for high temperature fuel cladding is becoming one of the major challenging tasks. Austenitic stainless steels with excellent corrosion resistance are often susceptible to stress corrosion cracking upon SCW exposure. Low-Cr steels such as P91 exhibit good high-temperature mechanical properties, but the lack of sufficient Cr content makes this group of alloys corrode too fast. One possible solution is to use coatings or surface modification techniques to improve the surface resistance to corrosion. In this study, we investigated the effect of surface modification on commercial 316L stainless steel. Surface modification by mechanical deformation has marked improvement in corrosion resistance during SCW exposure. Possible mechanisms for such improvement are discussed.
Highlights
The Canadian supercritical water reactor (SCWR) Concept will operate at a core outlet temperature of 625 ̊C and 25 MPa of pressure
The Canadian SCWR Concept will operate at a core outlet temperature of 625 ̊C and 25 MPa of pressure
The depth of the deformed zone depends on machining process and materials properties. Such shallow deformation zone is very difficult to be captured by conventional metallographic cross-sectioning, and Scanning Electron Microscope (SEM) examinations do not provide enough contrast to characterize this relatively shallow deformation zone
Summary
The Canadian SCWR Concept will operate at a core outlet temperature of 625 ̊C and 25 MPa of pressure. The peak cladding temperature can be as high as 800 ̊C. Cladding components are designed to be thin in order to improve neutron efficiency. High-temperature corrosion resistance in supercritical fluid is one of the key design requirements for in-core and out-of-core components. Corrosion resistance of commonly recognized alloy groups including Ni-based super alloys, austenitic stainless steels and ferritic/martensitic (F/M) steels was summarized by Allen et al [1]. F/M steels develop a thick but mechanically stable oxide layer, while austenitic stainless steels develop thinner oxide layer. Ni-based alloys appear to form very thin sur-
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