Mock-up test results of monoblock-type CFC divertor armor for JT-60SA

• Published in: Fusion engineering and design Vol. 84; no. 2; pp. 949 - 952
• Main Authors: Higashijima, S., Sakurai, S., Suzuki, S., Yokoyama, K., Kashiwa, Y., Masaki, K., Shibama, Y.K., Takechi, M., Shibanuma, K., Sakasai, A., Matsukawa, M., Kikuchi, M.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.06.2009; Elsevier
• Subjects: Applied sciences; Armor; Brazed joints; CFC; Chlorofluorocarbons; Controled nuclear fusion plants; Divertor; Domestic; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fracture mechanics; Heat flux; Heat transfer; High heat flux; Installations for energy generation and conversion: thermal and electrical energy; JT-60SA; Monoblock; Tokamak devices; CFC; Monoblock; JT-60SA; Divertor; High heat flux; Tokamak; Cooling; Fiber reinforced material; Heat flow; Composite material; Optimization; Research and development; Nuclear fusion reactor; Copper; Carbon fiber
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2009.02.021

The JT-60 Super Advanced (JT-60SA) tokamak project starts under both the Japanese domestic program and the international program “Broader Approach”. The maximum heat flux to JT-60SA divertor is estimated to ∼15 MW/m 2 for 100 s. Japan Atomic Energy Agency (JAEA) has developed a divertor armor facing high heat flux in the engineering R&D for ITER, and it is concluded that monoblock-type CFC divertor armor is promising for JT-60SA. The JT-60SA armor consists of CFC monoblocks, a cooling CuCrZr screw-tube, and a thin oxygen-free high conductivity copper (OFHC-Cu) buffer layer between the CFC monoblock and the screw-tube. CFC/OFHC-Cu and OFHC-Cu/CuCrZr joints are essential for the armor, and these interfaces are brazed. Needed improvements from ITER engineering R&D are good CFC/OFHC-Cu and OFHC-Cu/CuCrZr interfaces and suppression of CFC cracking. For these purposes, metalization inside CFC monoblock is applied, and we confirmed again that the mock-up has heat removal capability in excess of ITER requirement. For optimization of the fabrication method and understanding of the production yield, the mock-ups corresponding to quantity produced in one furnace at the same time is also produced, and the half of the mock-ups could remove 15 MW/m 2 as required. This paper summarizes the recent progress of design and mock-up test results for JT-60SA divertor armor.