Published March 2014 | Version v1
Journal article

The ITER blanket system design challenge

  • 1. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul-lez-Durance (France)
  • 2. Southwestern Institute of Physics (China ITER Domestic Agency), P.O. Box 585, No. 5, Huangjing Road, Shuangliu County, Chengdu 610225, Sichuan (China)
  • 3. ITER Korea, National Fusion Research Institute (NFRI) 169-148 Gwahak-Ro, Yuseong-Gu, Daejeon 305-806 (Korea, Republic of)
  • 4. N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Malaya Krasnoselskaya Str. 2/8, Moscow, 107140 (Russian Federation)
  • 5. Efremov Institute, 3 Doroga na Metallostroy, Metallostroy, St. Petersburg, 196641 (Russian Federation)
  • 6. MS-1129, PO Box 5800, Sandia National Laboratories, Albuquerque, NM 87185-1129,USA (United States)
  • 7. Fusion for Energy, ITER Department, Torres Diagonal Litoral B3, c/Josep Plá n.2, 08019 Barcelona (Spain)

Description

This paper summarizes the latest progress in the ITER blanket system design as it proceeds through its final design phase with the Final Design Review planned for Spring 2013. The blanket design is constrained by demanding and sometime conflicting design and interface requirements from the plasma and systems such as the vacuum vessel, in-vessel coils and blanket manifolds. This represents a major design challenge, which is highlighted in this paper with examples of design solutions to accommodate some of the key interface and integration requirements. (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/0029-5515/54/3/033004

Additional details

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
54
Journal Issue
3
Journal Page Range
[18 p.]
ISSN
0029-5515
CODEN
NUFUAU

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46034227
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
CONTAINERS; DESIGN; ELECTRIC COILS; INTERFACES; ITER TOKAMAK; PLASMA
Descriptors DEC
CLOSED PLASMA DEVICES; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information