Development of vanadium-base alloys for fusion first-wall—blanket applications
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In this paper, vanadium alloys with (3-5)% Cr and (3 -5) % Ti have been identified as a leading candidate material for fusion first-wall-blanket applications.About:
This article is published in Fusion Engineering and Design.The article was published on 1995-03-03 and is currently open access. It has received 80 citations till now. The article focuses on the topics: Liquid metal & Alloy.read more
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Status of vanadium alloys for fusion reactors
TL;DR: In this paper, the effects of dynamically-charged helium on vanadium alloys and their damage behavior are investigated for efficient vanadium alloy development and prediction of materials life in service, and recent developments of insulator coatings and welding are also covered.
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Reference vanadium alloy V4Cr4Ti for fusion application
TL;DR: In this paper, the US reference vanadium alloy, V4Cr4Ti alloy, was identified as the reference material for the first-wall/blanket applications.
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An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems
TL;DR: The viability of advanced Pb- or PbBi-cooled fast reactor systems will depend on the development of classes of materials that can operate over the temperature range 650-1200°C as mentioned in this paper.
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Vanadium-base alloys for fusion first-wall/blanket applications
TL;DR: An overview of the development of vanadium alloys for fusion applications and a summary of key issues requiring further research is presented in this paper, where the authors also present a characterization of baseline properties, corrosion/compatibility, and effects of irradiation on the properties.
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Liquid metal compatibility issues for test blanket modules
TL;DR: In this article, a solution to the magnetohydrodynamic (MHD) problem for the V-Li concept may be attainable using multi-layer coatings or a flow channel insert with vanadium in contact with the flowing Li instead of a ceramic insulating layer.
References
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Vanadium-base alloys for fusion reactor applications — a review
TL;DR: In this paper, the authors present a review of the structural material requirements, a summary of the materials data base for selected vanadium-base alloys with emphasis on the V-15Cr-5Ti alloy, and a comparison of projected performance characteristics compared to other candidate alloys.
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Overview of the Blanket Comparison and Selection Study
Dale L. Smith,Charles C. Baker,Dai-Kai Sze,G.D. Morgan,Mohamed A. Abdou,S.J. Piet,K.R. Schultz,Ralph W. Moir,James D. Gordon +8 more
TL;DR: A comprehensive Blanket Comparison and Selection Study was conducted to evaluate proposed D-T fusion reactor blanket concepts and to identify those concepts that offer the greatest potential for fusion reactor applications.
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Effects of neutron irradiation and hydrogen on ductile-brittle transition temperatures of V-Cr-Ti alloys
TL;DR: The effects of neutron irradiation and hydrogen on the ductile- brittle transition temperatures (DBTTs) of unalloyed vanadium and V-Cr-Ti alloys were determined from Charpy-impact tests on 1/3 ASTM standard size specimens and from impact tests on 3-mm diameter discs as discussed by the authors.
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Swelling of neutron-irradiated vanadium alloys☆
TL;DR: In this article, the swelling of unalloyed vanadium and vanadium alloys containing Cr, Ti, Si, Fe, Zr, W, Mo, and Ni was determined after neutron irradiation at 420 and 600°C to 17-84 dpa in the FFTF-MOTA reactor facility.
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Tensile properties and microstructure of helium-injected and reactor-irradiated V-20 Ti
TL;DR: In this article, the effect of preinjected helium followed by neutron irradiation on the mechanical properties and microstructure of V-20% Ti was investigated and the ojective of this work was to determine the effect.