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Fusion Science and Technology Volume 46, 2004 - Issue 4
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Technical Paper

Development of ITER Divertor Vertical Target with Annular Flow Concept—II: Development of Brazing Technique for CFC/CuCrZr Joint and Heating Test of Large-Scale Mock-Up

K. EzatoJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
M. DairakuJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
M. TaniguchiJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
K. SatoJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
S. SuzukiJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
M. AkibaJapan Atomic Energy Research Institute, Department of Fusion Engineering Research 801-1, Mukoyama, Naka-machi, Naka-gun, Ibaraki 311-0193, Japan
,
C. IbbottITER Garching Joint Work Site, Max-Plank-Institut für Plasmaphyik Boltzmannstrasse 2, 85748, Garching, Germany
&
R. TiveyITER Garching Joint Work Site, Max-Plank-Institut für Plasmaphyik Boltzmannstrasse 2, 85748, Garching, Germany
 show all
Pages 530-540 | Published online: 27 Mar 2017

REFERENCES

  • R. Tivey, M. Akiba, D. Driemeyer, I. Mazul, M. Merola, and M. Ulrickson, “ITER R&D: Vacuum Vessel and In-Vessel Components: Divertor Cassette,” Fusion Eng. Des., 55, 219 (2001).
  • R. Tivey et al., “ITER Divertor, Design Issues and Research and Development,” Fusion Eng. Des., 46, 207 (1999).
  • S. Suzuki, T. Suzuki, M. Araki, K. Nakamura, and M. Akiba, “Development of Divertor Plate with CFCs Bonded onto DSCu Cooling Tube For Fusion Reactor Application,” J. Nuc. Mater., 258–263, 318 (1998).
  • S. Suzuki, K. Sato, K. Ezato, K. Yokoyama, M. Dairaku, K. Nakamura, and M. Akiba, “Development of Divertor High Heat Flux Components for ITER in JAERI,” Phys. Scripta, T81, 89 (1999).
  • S. Suzuki, K. Ezato, K. Sato, K. Nakamura, and M. Akiba, “Thermal Fatigue Damage of the Divertor Plate,” Fusion Eng. Des., 49–50, 343 (2000).
  • C. Ibbott et al., “Design Issues and Cost Implications of RTO:RC-ITER Divertor,” Fusion Eng. Des., 49–50, 217 (2000).
  • C. Ibbott et al., “Overview of the Engineering Design of ITER Divertor,” Fusion Eng. Des., 56–57, 243 (2001).
  • G. Janeschitzetal., “Overview of the Divertor Design and Its Integration into RTO/RC-ITER,” Fusion Eng. Des., 49–50, 107 (2000).
  • K. Ezato et al., “Development of ITER Divertor Vertical Target with Annular Flow Concept—I: Thermal-Hydraulic Characteristics of Annular Swirl Tube,” Fusion Sci. Technol., 46, 521 (2004).
  • J. W. Davis and G. M. Kalinin, “Material Properties and Design Requirements for Copper Alloys Used in ITER,” J. Nuc. Mater., 258–263, 323 (1998).
  • G. Kalinin et al., “Assessment and Selection of Materials for ITER In-Vessel Components,” J. Nuc. Mater., 283–287, 10 (2000).
  • T. Hino and M. Akiba, “Japanese Developments of Fusion Reactor Plasma Facing Components,” Fusion Eng. Des., 49–50, 97 (2000).
  • “ABAQUS User’s Manual 5.8,” Hibbit, Karlson, and Sorenson, Inc., Providence, Rhode Island (1996).

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