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Johnson, W.R.; Smith, J.P.
General Atomics, San Diego, CA (United States). Funding organisation: USDOE Office of Energy Research, Washington, DC (United States)1998
General Atomics, San Diego, CA (United States). Funding organisation: USDOE Office of Energy Research, Washington, DC (United States)1998
AbstractAbstract
[en] Vanadium chromium titanium alloys are attractive materials for fusion reactors because of their high temperature capability and their potential for low neutron active and rapid activation decay. A V-4Cr-4Ti alloy has been selected in the U.S. as the current leading candidate vanadium alloy for future use in fusion reactor structural applications. General Atomics (GA), in conjunction with the Department of Energy's (DOE) DIII-D Program, is carrying out a plan for the utilization of this vanadium alloy in the DIII-D tokamak. The plan will culminate in the fabrication, installation, and operation of a V-4Ti alloy structure in the DIII-D Radiative Divertor (RD) upgrade. The deployment of vanadium alloy will provide a meaningful step in the development and technology acceptance of this advanced material for future fusion power devices. Under a GA contract and material specification, an industrial scale 1200 kg heat (ingot) of a V-4Cr-4Ti alloy has been produced and converted into product forms by Wah Chang of Albany, Oregon (WCA). To assure the proper control of minor and trace impurities which affect the mechanical and activation behavior of this vanadium alloy, selected lots of raw vanadium base metal were processed by aluminothermic reduction of high purity vanadium oxide, and were then electron beam melted into two high purity vanadium ingots. The ingots were then consolidated with high purity Cr and Ti, and double vacuum-arc melted to obtain a 1200 kg V-4Cr-4Ti alloy ingot. Several billets were extruded from the ingot, and were then fabricated into plate, sheet, and rod at WCA. Tubing was subsequently processed from plate material. The chemistry and fabrication procedures for the product forms were specified on the basis of experience and knowledge gained from DOE Fusion Materials Program studies on previous laboratory scale heats and a large scale ingot (500 kg)
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Jan 1998; 13 p; 8. international conference on fusion reactor materials (ICFRM); Sendai (Japan); 26-31 Oct 1997; CONF-971090--; CONTRACT AC03-89ER51114; ALSO AVAILABLE FROM OSTI AS DE98002633; NTIS; INIS; US GOVT. PRINTING OFFICE DEP
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Report
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Conference; Numerical Data
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