Design evolution and integration of the ITER in-vessel components

A. Martin; B. Calcagno; Ph Chappuis; E. Daly; G. Dellopoulos; A. Furmanek; S. Gicquel; P. Heitzenroeder; Chen Jiming; M. Kalish; D. H. Kim; S. Khomiakov; A. Labusov; A. Loarte; M. Loughlin; M. Merola; R. Mitteau; E. Polunovski; R. Raffray; S. Sadakov; M. Ulrickson; F. Zacchia; Zhang Fu

doi:10.1016/j.fusengdes.2013.01.004

Design evolution and integration of the ITER in-vessel components

A. Martin, B. Calcagno, Ph Chappuis, E. Daly, G. Dellopoulos, A. Furmanek, S. Gicquel, P. Heitzenroeder, Chen Jiming, M. Kalish, D. H. Kim, S. Khomiakov, A. Labusov, A. Loarte, M. Loughlin, M. Merola, R. Mitteau, E. Polunovski, R. Raffray, S. SadakovM. Ulrickson, F. Zacchia, Zhang Fu

Research output: Contribution to journal › Article › peer-review

10 Scopus citations

Abstract

The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blanket system has been redesigned to include first wall (FW) shaping, to upgrade the FW heat removal capability and to allow for an "in situ" replacement. The blanket manifold system has been redesigned to improve leak detection and localisation. The introduction of a new set of in-vessel coils and the design evolution of the blanket system while the ITER project was entering the procurement phase have proven to be a major engineering challenge. This paper describes the status of the redesign of the in-vessel components and the associated integration issues.

Original language	English
Pages (from-to)	1955-1959
Number of pages	5
Journal	Fusion Engineering and Design
Volume	88
Issue number	9-10
DOIs	https://doi.org/10.1016/j.fusengdes.2013.01.004
State	Published - Oct 2013
Externally published	Yes

Keywords

Blankets
ITER
In vessel coils
In vessel components

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2013.01.004

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Martin, A., Calcagno, B., Chappuis, P., Daly, E., Dellopoulos, G., Furmanek, A., Gicquel, S., Heitzenroeder, P., Jiming, C., Kalish, M., Kim, D. H., Khomiakov, S., Labusov, A., Loarte, A., Loughlin, M., Merola, M., Mitteau, R., Polunovski, E., Raffray, R., ... Fu, Z. (2013). Design evolution and integration of the ITER in-vessel components. Fusion Engineering and Design, 88(9-10), 1955-1959. https://doi.org/10.1016/j.fusengdes.2013.01.004

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title = "Design evolution and integration of the ITER in-vessel components",

abstract = "The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blanket system has been redesigned to include first wall (FW) shaping, to upgrade the FW heat removal capability and to allow for an {"}in situ{"} replacement. The blanket manifold system has been redesigned to improve leak detection and localisation. The introduction of a new set of in-vessel coils and the design evolution of the blanket system while the ITER project was entering the procurement phase have proven to be a major engineering challenge. This paper describes the status of the redesign of the in-vessel components and the associated integration issues.",

keywords = "Blankets, ITER, In vessel coils, In vessel components",

author = "A. Martin and B. Calcagno and Ph Chappuis and E. Daly and G. Dellopoulos and A. Furmanek and S. Gicquel and P. Heitzenroeder and Chen Jiming and M. Kalish and Kim, {D. H.} and S. Khomiakov and A. Labusov and A. Loarte and M. Loughlin and M. Merola and R. Mitteau and E. Polunovski and R. Raffray and S. Sadakov and M. Ulrickson and F. Zacchia and Zhang Fu",

year = "2013",

month = oct,

doi = "10.1016/j.fusengdes.2013.01.004",

language = "English",

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Martin, A, Calcagno, B, Chappuis, P, Daly, E, Dellopoulos, G, Furmanek, A, Gicquel, S, Heitzenroeder, P, Jiming, C, Kalish, M, Kim, DH, Khomiakov, S, Labusov, A, Loarte, A, Loughlin, M, Merola, M, Mitteau, R, Polunovski, E, Raffray, R, Sadakov, S, Ulrickson, M, Zacchia, F & Fu, Z 2013, 'Design evolution and integration of the ITER in-vessel components', Fusion Engineering and Design, vol. 88, no. 9-10, pp. 1955-1959. https://doi.org/10.1016/j.fusengdes.2013.01.004

TY - JOUR

T1 - Design evolution and integration of the ITER in-vessel components

AU - Martin, A.

AU - Calcagno, B.

AU - Chappuis, Ph

AU - Daly, E.

AU - Dellopoulos, G.

AU - Furmanek, A.

AU - Gicquel, S.

AU - Heitzenroeder, P.

AU - Jiming, Chen

AU - Kalish, M.

AU - Kim, D. H.

AU - Khomiakov, S.

AU - Labusov, A.

AU - Loarte, A.

AU - Loughlin, M.

AU - Merola, M.

AU - Mitteau, R.

AU - Polunovski, E.

AU - Raffray, R.

AU - Sadakov, S.

AU - Ulrickson, M.

AU - Zacchia, F.

AU - Fu, Zhang

PY - 2013/10

Y1 - 2013/10

N2 - The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blanket system has been redesigned to include first wall (FW) shaping, to upgrade the FW heat removal capability and to allow for an "in situ" replacement. The blanket manifold system has been redesigned to improve leak detection and localisation. The introduction of a new set of in-vessel coils and the design evolution of the blanket system while the ITER project was entering the procurement phase have proven to be a major engineering challenge. This paper describes the status of the redesign of the in-vessel components and the associated integration issues.

AB - The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blanket system has been redesigned to include first wall (FW) shaping, to upgrade the FW heat removal capability and to allow for an "in situ" replacement. The blanket manifold system has been redesigned to improve leak detection and localisation. The introduction of a new set of in-vessel coils and the design evolution of the blanket system while the ITER project was entering the procurement phase have proven to be a major engineering challenge. This paper describes the status of the redesign of the in-vessel components and the associated integration issues.

KW - Blankets

KW - ITER

KW - In vessel coils

KW - In vessel components

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DO - 10.1016/j.fusengdes.2013.01.004

M3 - Article

AN - SCOPUS:84884984416

SN - 0920-3796

VL - 88

SP - 1955

EP - 1959

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 9-10

ER -

Design evolution and integration of the ITER in-vessel components

Abstract

Keywords

UN SDGs

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