Current status on the detailed design and development of fabrication techniques for the ITER blanket shield block in Korea

Kim, Duck-Hoi; Cho, Seungyon; Ahn, Min Cheol; Lee, Eunseok; Jung, Ki Jung; Kim, Do-Hyeong

doi:10.1016/j.fusengdes.2008.08.006

Cited by 6 publications

(3 citation statements)

References 6 publications

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“…Back of FW beam : NL = 7.10 × 10 6 · e −12.5x (2) where NL is the nuclear heating rate [W/m 3 ]; x is the radial distance from first wall surface [m]. Fig.…”

Section: Design Analysis Of Shield Block 01 and 02mentioning

confidence: 99%

“…The basic SB cooling concept of CDR models was poloidal cooling considering the benefits such as its manufacturability improvement [1][2][3][4]. After CDR the interfaces with blanket First Wall (FW) or Vacuum Vessel (VV) were changed drastically, therefore cooling channels in a shield block were redesigned following the design protocol, relevant codes and standards.…”

Section: Introductionmentioning

confidence: 99%

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Cooling optimization for preliminary design of ITER blanket shield block

Kim

Ha²,

Choi³

et al. 2012

Fusion Engineering and Design

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“…Back of FW beam : NL = 7.10 × 10 6 · e −12.5x (2) where NL is the nuclear heating rate [W/m 3 ]; x is the radial distance from first wall surface [m]. Fig.…”

Section: Design Analysis Of Shield Block 01 and 02mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Cooling optimization for preliminary design of ITER blanket shield block

Kim

Ha²,

Choi³

et al. 2012

Fusion Engineering and Design

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“…Several Be/CuCrZr mock-ups have been tested in the electron beam facility JUDITH-1 (Juelich, Germany) and compared with the reference material S65C grade [42]. Also ongoing are fabrication design and R&D activities for the shield block [43], the blanket manifolds, the blanket module to vacuum vessel attachment system and remote handling experimental demonstrations. Procurement of the blanket system will start in late 2012.…”

Section: Blanket and First Wallmentioning

confidence: 99%

ITER project and fusion technology

Takatsu

2011

Nucl. Fusion

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In the sessions of ITR, FTP and SEE of the 23rd IAEA Fusion Energy Conference, 159 papers were presented in total, highlighted by the remarkable progress of the ITER project: ITER baseline has been established and procurement activities have been started as planned with a target of realizing the first plasma in 2019; ITER physics basis is sound and operation scenarios and operational issues have been extensively studied in close collaboration with the worldwide physics community; the test blanket module programme has been incorporated into the ITER programme and extensive R&D works are ongoing in the member countries with a view to delivering their own modules in a timely manner according to the ITER master schedule. Good progress was also reported in the areas of a variety of complementary activities to DEMO, including Broader Approach activities and long-term technology. This paper summarizes the highlights of the papers presented in the ITR, FTP and SEE sessions with a minimum set of background information.

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