摘要
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.
