ITER first wall/shield blanket

The blanket system comprises first wall/shield modules which are supported on a structural shell called a Back Plate containing water channels for cooling the modules. A modular design of the first wall/shield was chosen to allow independent maintenance through the horizontal mid-plane ports using i...

Full description

Saved in:
Bibliographic Details
Published inFusion engineering and design Vol. 39; no. 1-4; pp. 585 - 592
Main Authors Ioki, K., Barabaschi, P., Bruno, L., Cardella, A., Danner, W., Elio, F., Hechler, M., Kodama, T., Lodato, A., Loesser, D., Lousteau, D., Mattas, R., Miki, N., Mohri, K., Parker, R., Raffray, R., Strebkov, Y., Tachikawa, N., Takatsu, H., Williamson, D., Yamada, M.
Format Journal Article Conference Proceeding
LanguageEnglish
Published Amsterdam Elsevier B.V 01.09.1998
New York, NY Elsevier Science
Subjects
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Installations for energy generation and conversion: thermal and electrical energy
Tokamak
Design criterion
Wall
Shield
Joining
Mechanical joint
Modeling
Nuclear fusion reactor
Blanket
Welded joint
Stainless steel
Strength
Structural analysis
Online AccessGet full text

Cover

More Information
Summary:The blanket system comprises first wall/shield modules which are supported on a structural shell called a Back Plate containing water channels for cooling the modules. A modular design of the first wall/shield was chosen to allow independent maintenance through the horizontal mid-plane ports using in-vessel remote handling equipment. The modules are mechanically attached to the back plate for assembly and maintenance. The first wall/shield modules can be replaced with breeding modules for the EPP. In the first wall (FW) region, the water is contained in 316 LN stainless steel pipes surrounded by a copper heat sink except in high heat flux regions where copper pipes with a stainless steel liner are used in the limiter and baffles. The plasma facing surface of the FW will be beryllium except for the lower region of the baffles, where tungsten is used. Electromagnetic analysis and structural analysis has been performed on the back plate and FW/shield modules during a plasma disruption and for a VDE with toroidally asymmetric halo currents. A major R and D project is being conducted to provide needed input for design of the blanket system and to confirm the fabrication technology.
ISSN:0920-3796
1873-7196
DOI:10.1016/S0920-3796(98)00201-4