Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
4921329 | Fusion Engineering and Design | 2016 | 5 Pages |
Abstract
Japan Atomic Energy Agency (JAEA) is in progress for technology demonstration toward Full-tungsten (W) ITER divertor outer vertical target (OVT), especially, W monoblock technology that needs to withstand the repetitive heat load as high as 20Â MW/m2 for 10Â s. Under the framework of the W divertor qualification program developed ITER organization, JAEA as Japanese Domestic Agency (JADA) manufactured seven full-scale plasma-facing unit (PFU) prototypes with the Japanese industries. Four prototypes that have 146Â W monoblock joint with casted copper (Cu) interlayer passed successfully the ultrasonic testing. In the other three prototypes that have the different W/Cu interlayer joint, joint defects were found. The dimension measurements reveal the requirements of the gap between W monoblocks and the surface profile of PFU are feasible.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Koichiro Ezato, Satoshi Suzuki, Yohji Seki, Hirokazu Yamada, Tomoyuki Hirayama, Kenji Yokoyama, Frederic Escourbiac, Takeshi Hirai,