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Volumn 46, Issue 4, 2004, Pages 530-539

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

Author keywords

CFC CuCrZr joining; Divertor; High heat flux testing

Indexed keywords

COMPOSITE MATERIALS; FINITE ELEMENT METHOD; HEAT FLUX; HEAT TREATMENT; ION BEAMS; MECHANICAL PROPERTIES; STAINLESS STEEL; STRENGTH OF MATERIALS;

EID: 33748548394     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst04-a588     Document Type: Article
Times cited : (14)

References (13)
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  • 3
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    • Development of divertor plate with CFCs bonded onto DSCu cooling tube for fusion reactor application
    • 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).
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  • 6
    • 0034318321 scopus 로고    scopus 로고
    • Design issues and cost implications of RTO:RC-ITER divertor
    • C. IBBOTT et al., "Design Issues and Cost Implications of RTO:RC-ITER Divertor," Fusion Eng. Des., 49-50, 217 (2000).
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 217
    • Ibbott, C.1
  • 7
    • 0035483581 scopus 로고    scopus 로고
    • Overview of the engineering design of ITER divertor
    • C. IBBOTT et al., "Overview of the Engineering Design of ITER Divertor," Fusion Eng. Des., 56-57, 243 (2001).
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    • Ibbott, C.1
  • 8
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    • Overview of the divertor design and its integration into RTO/RC-ITER
    • G. JANESCHITZ et al., "Overview of the Divertor Design and Its Integration into RTO/RC-ITER," Fusion Eng. Des., 49-50, 107 (2000).
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 107
    • Janeschitz, G.1
  • 9
    • 19644366832 scopus 로고    scopus 로고
    • Development of ITER divertor vertical target with annular flow concept - I: Thermal-hydraulic characteristics of annular swirl tube
    • 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).
    • (2004) Fusion Sci. Technol. , vol.46 , pp. 521
    • Ezato, K.1
  • 10
    • 0032179910 scopus 로고    scopus 로고
    • Material properties and design requirements for copper alloys used in ITER
    • 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).
    • (1998) J. Nuc. Mater. , vol.258-263 , pp. 323
    • Davis, J.W.1    Kalinin, G.M.2
  • 11
    • 4243825924 scopus 로고    scopus 로고
    • Assessment and selection of materials for ITER in-vessel components
    • G. KALININ et al., "Assessment and Selection of Materials for ITER In-Vessel Components," J. Nuc. Mater., 283-287, 10 (2000).
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  • 12
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    • Japanese developments of fusion reactor plasma facing components
    • T. HINO and M. AKIBA, "Japanese Developments of Fusion Reactor Plasma Facing Components," Fusion Eng. Des., 49-50, 97 (2000).
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 97
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  • 13
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.