ITER will be constructed and has its first plasma at 2016. It will demonstrate the integration of technologies for reactors and serve as a test facility for advanced components such as blankets. China has joined the p...ITER will be constructed and has its first plasma at 2016. It will demonstrate the integration of technologies for reactors and serve as a test facility for advanced components such as blankets. China has joined the program and will have her contribution to its construction, operation and so on. One of the in-vessel components fabricated by China is the shield blanket, which consists of first wall （FW） and shield blocks. FW is a joint of Be/Cu/SS, with Be as plasma facing material.展开更多
High temperature HIP joining technology of Be/CuCrZr alloy or DS-Cu has been applied by Europe and Japan for the frabrication of ITER first wall. At the first stage of our research, high temperature HIP joining of Be/...High temperature HIP joining technology of Be/CuCrZr alloy or DS-Cu has been applied by Europe and Japan for the frabrication of ITER first wall. At the first stage of our research, high temperature HIP joining of Be/CuCrZr alloy was investigated by referencing their successful experience and Ti was selected as interlayer. Since the first wall will receive high heat flux during ITER operation, the heat load resistance capabilities, in particular thermal fatigue property is a crucial criterion of FW mock-ups. In order to test the heat load resistance capabilities of Be/CuCrZr joints, an electron beam heat load facility with beryllium handling capability has been constructed and heat removal performances and thermal cycling tests of Be/CuCrZr joints were carried out.展开更多
文摘ITER will be constructed and has its first plasma at 2016. It will demonstrate the integration of technologies for reactors and serve as a test facility for advanced components such as blankets. China has joined the program and will have her contribution to its construction, operation and so on. One of the in-vessel components fabricated by China is the shield blanket, which consists of first wall （FW） and shield blocks. FW is a joint of Be/Cu/SS, with Be as plasma facing material.
文摘High temperature HIP joining technology of Be/CuCrZr alloy or DS-Cu has been applied by Europe and Japan for the frabrication of ITER first wall. At the first stage of our research, high temperature HIP joining of Be/CuCrZr alloy was investigated by referencing their successful experience and Ti was selected as interlayer. Since the first wall will receive high heat flux during ITER operation, the heat load resistance capabilities, in particular thermal fatigue property is a crucial criterion of FW mock-ups. In order to test the heat load resistance capabilities of Be/CuCrZr joints, an electron beam heat load facility with beryllium handling capability has been constructed and heat removal performances and thermal cycling tests of Be/CuCrZr joints were carried out.
