Title of article
Ferritic–Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validation
Author/Authors
Salavy، نويسنده , , J.-F. and Aiello، نويسنده , , G. and Aubert، نويسنده , , P. and Boccaccini، نويسنده , , L.V. and Daichendt، نويسنده , , M. and De Dinechin، نويسنده , , G. and Diegele، نويسنده , , E. and Giancarli، نويسنده , , L.M. and Lنsser، نويسنده , , R. and Neuberger، نويسنده , , H. and Poitevin، نويسنده , , Y. and Stephan، نويسنده , , Y. and Rampal، نويسنده , , G. and Rigal، نويسنده , , E.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2009
Pages
5
From page
922
To page
926
Abstract
The Helium-Cooled Lithium-Lead and the Helium-Cooled Pebble Bed are the two breeding blankets concepts for the DEMO reactor which have been selected by EU to be tested in ITER in the framework of the Test Blanket Module projects. They both use a 9%CrWVTa Reduced Activation Ferritic–Martensitic steel, called EUROFER, as structural material and helium as coolant. This paper gives an overview of the status of the EUROFER qualification program and discusses the future needs for design criteria requirements and fabrication validation.
Journal title
Journal of Nuclear Materials
Serial Year
2009
Journal title
Journal of Nuclear Materials
Record number
1366397
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