“…Addition of Si, Al and Y and increase in Cr level were shown to be effective in suppressing the corrosion in air and water environment, respectively. 30,31) Vanadium alloys are known to lose their ductility when hydrogen is charged. It was reported that the loss of ductility by hydrogen was enhanced by impurity oxygen.…”
Section: Corrosion Compatibility and Hydrogen Effectsmentioning
Vanadium alloys are attractive candidate structural materials for breeding blanket of fusion reactors because of their low activation properties and high temperature strength. Studies on various blanket designs are being carried out using vanadium alloys as structural materials and liquid lithium or molten salt Flibe as breeding and coolant materials. Recently significant progress in fabrication technology has been made for vanadium alloys through a program of producing large ingots of high purity V-4Cr-4Ti (NIFS-HEATs). Fundamental understandings on the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, corrosion and compatibility in various environments were enhanced. New promising candidates were identified for the MHD insulator coating. Among the remaining critical issues are the effects of transmutant helium on mechanical properties and development of long life MHD coating. Development of vanadium alloys will be carried out in coordination with IFMIF and ITER-TBM schedules as essential tools for verification of their performance in fusion blanket environments.
“…Addition of Si, Al and Y and increase in Cr level were shown to be effective in suppressing the corrosion in air and water environment, respectively. 30,31) Vanadium alloys are known to lose their ductility when hydrogen is charged. It was reported that the loss of ductility by hydrogen was enhanced by impurity oxygen.…”
Section: Corrosion Compatibility and Hydrogen Effectsmentioning
Vanadium alloys are attractive candidate structural materials for breeding blanket of fusion reactors because of their low activation properties and high temperature strength. Studies on various blanket designs are being carried out using vanadium alloys as structural materials and liquid lithium or molten salt Flibe as breeding and coolant materials. Recently significant progress in fabrication technology has been made for vanadium alloys through a program of producing large ingots of high purity V-4Cr-4Ti (NIFS-HEATs). Fundamental understandings on the effects of interstitial impurities (C, N, O) on mechanical properties, radiation effects on microstructure and mechanical properties, corrosion and compatibility in various environments were enhanced. New promising candidates were identified for the MHD insulator coating. Among the remaining critical issues are the effects of transmutant helium on mechanical properties and development of long life MHD coating. Development of vanadium alloys will be carried out in coordination with IFMIF and ITER-TBM schedules as essential tools for verification of their performance in fusion blanket environments.
“…Addition of Si, Al and Y and increase in Cr level were shown to be effective in suppressing the corrosion in air and water environment, respectively. 23,24) There have been continuous efforts in Japan to improve vanadium alloys by changing composition from V-4Cr-4Ti or to change the fabrication processes. Figure 11 indicates representing results of the efforts.…”
Japanese activities on fusion structural materials R&D have been well organized under the coordination of university programs and JAERI/NIMS programs more than two decades. Where, two categories of structural materials have been studied, those are; reduced activation ferritic/martensitic steels (RAFs) as reference material and vanadium alloys and SiC/SiC composite materials as advanced materials. The R&D histories of these candidate materials and the present status in Japan are reviewed with the brief explanation of Japanese strategy and current status of fusion reactor engineering R&D.
“…The re-emission of the retained helium from the wall due to the heat load and the particle bombardment leads to the fuel dilution, so that it is necessary to evaluate the helium retention and desorption behaviors for the material used as the first wall. In addition, it is known that some vanadium alloys are rather oxidized [3]. The surface oxidation affected the deuterium retention and desorption properties of alloys such as reduced activation ferritic steel [4].…”
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