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AbstractAbstract
[en] China will manufacture 10% of the ITER first wall (FW) panels as her in-kind contribution to ITER. To ensure the manufactured panel in required quality, the fabrication technology should be qualified by fabrication and testing FW qualification mock-ups. One of the key issues for the fabrication is the formation of Be/Cu intermetallic phases that increase the brittleness of the joint. Therefore, the main objective of this study on the joining technology is to find ways to reduce the brittle phase formation, and the fabrication of a mockup satisfying the ITER-FW requirements. China started the study on the joining technology in 2005. Various interlayer of Ti, Al, AlSiMg alloy and Cu in forms of foil and coating were investigated with the joining method of HIPing at high temperature (> 850 deg C) and relatively low temperature (580 deg C). By analysis of the interface microstructure and measurement of bounding strength, a relatively optimized joining technology was obtained in 2006. The technology was that (1) joining Be to CuCrZr alloy by HIPing at 580 deg C / 140 MPa/ 2 hr with Ti/Cu interlayer of coating and (2) joining CuCrZr to SS (stainless steel) plate and tubes by HIPing at 1040 deg C / 130 MPa/ 2 hr without interlayer material. It is required that the FW mockup and the semi-prototype should use qualified materials. Within one year, high purity Be pebbles (> 99.5%) was produced in China. With a vacuum-hot-pressing (VHP) method of powder processing, small ingots of Chinese VHP-Be of > 99% purity was made. Its BeO content was less than 1%. Chemical composition and microstructure were analyzed; both meet the ITER's requirement. The physical and tensile properties of the material are similar to those of the VHP-S65C-Be made in Brushwelman in US. In the past two years, to improve the joining technology, several FW mock-ups have been fabricated. They were analyzed by NDT and destructively tested. Results showed that there was no interface defects larger than 2 mm in diameter. Ti3Cu4 inter-metallic phase was observed at the interface. Be/Cu bounding strength (shear test mode) reached up to more than 200 MPa at RT. The mechanical properties of CuCrZr alloy varied in the HIPing process. Both EU and China Cu alloy could satisfy the ITER requirement of the mechanical strength after the mock-up fabrication. However, only the alloy used in forged state could meet the requirement of grain size. (author)
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International Atomic Energy Agency, Division of Physical and Chemical Sciences, Physics Section, Vienna (Austria); Ecole Polytechnique Federale de Lausanne, Lausanne (Switzerland); 295 p; 2008; p. 177; FEC 2008: 22. IAEA fusion energy conference - 50th Anniversary Controlled Nuclear Fusion Research; Geneva (Switzerland); 13-18 Oct 2008; IT/P7--10; Also available on-line: http://www-pub.iaea.org/MTCD/Meetings/PDFplus/2008/cn165/cn165_BookOfAbstracts.pdf
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Report
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Conference
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ALKALINE EARTH METAL COMPOUNDS, ALLOYS, ASIA, BERYLLIUM COMPOUNDS, CARBON ADDITIONS, CHALCOGENIDES, CLOSED PLASMA DEVICES, ELECTRONIC EQUIPMENT, EQUIPMENT, FABRICATION, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS WORKING, MECHANICAL PROPERTIES, MICROSTRUCTURE, OXIDES, OXYGEN COMPOUNDS, POWER SUPPLIES, PRESSING, SIZE, STEELS, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTOR WALLS, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS, TRANSITION ELEMENT ALLOYS
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