Material migration studies with an ITER first wall panel proxy on EAST
نویسندگان
چکیده
منابع مشابه
Study on Characteristics of Dissimilar Material Joints for ITER First Wall
The first wall (FW) of ITER blanket includes beryllium (Be) armor tiles joined to CuCrZr heat sink with stainless steel (SS) cooling tube and backing plate in order to improve plasma performance and reduce thermal stress. Since these joints must withstand thermal and mechanical loads caused by the plasma and electromagnetic force, it is important to evaluate the strength and thermal fatigue lif...
متن کاملITER first wall fabrication technology in China
China has done R&Ds on the fabrication technology for ITER first wall (FW). The FW materials, such as the vacuum-hot-pressing (VHP) Be and ITER-grade CuCrZr alloys, have been developed in China. The Be plate showed good physical and mechanical properties, similar to S65C. The effect of fabrication process on mechanical strength of CuCrZr alloy was studied. Several FW qualification (FWQ) mock-up...
متن کاملSolid State Bonding of Beryllium-copper for an Iter First Wall Application
Several different joint assemblies were evaluated in support of a manufacturing technology for diffusion bonding a beryllium armor tile to a copper alloy heat sink for fusion reactor applications. Because beryllium reacts with all but a few elements to form intermetallic compounds, this study considered several different surface treatments as a means of both inhibiting these reactions and promo...
متن کاملProgress on the Development of the Fabrication Technology for the ITER First Wall in Korea
Korea is responsible for the procurement of the ITER first wall (FW) blanket modules 1, 2 and 6, and has been developing the fabrication technology of them. Joining Be, CuCrZr and stainless steel (SS) is the most important aspect of the FW and to derive the optimum joining conditions, several mock-ups with various temperatures and pressure conditions between CuCrZr, and SS and with various inte...
متن کاملErosion/redeposition analysis of the ITER first wall with convective and non-convective plasma transport
Sputtering erosion/redeposition is analyzed for ITER plasma facing components, with scrape-off layer (SOL) plasma convective radial transport and non-convective (diffusion-only) transport. The analysis uses the UEDGE and DEGAS codes to compute plasma SOL profiles and ion and neutral fluxes to the wall, TRIM-SP code to compute sputter yields, and REDEP/WBC code package for 3-D kinetic modeling o...
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ژورنال
عنوان ژورنال: Nuclear Fusion
سال: 2015
ISSN: 0029-5515,1741-4326
DOI: 10.1088/0029-5515/55/2/023013