Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket

H. Tanigawa; K. Shiba; A. Möslang; R. E. Stoller; R. Lindau; M. A. Sokolov; G. R. Odette; R. J. Kurtz; S. Jitsukawa

doi:10.1016/j.jnucmat.2011.05.023

Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket

H. Tanigawa, K. Shiba, A. Möslang, R. E. Stoller, R. Lindau, M. A. Sokolov, G. R. Odette, R. J. Kurtz, S. Jitsukawa

Advanced Nuclear Materials

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154 Scopus citations

Abstract

The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion energy demonstration reactor blankets. This includes manufacturing technology, the as-fabricated and irradiates material database and joining technologies. The review indicated that the manufacturing technology, joining technology and database accumulation including irradiation data are ready for initial design activity, and also identifies various issues that remain to be solved for engineering design activity and qualification of the material for international fusion material irradiation facility (IFMIF) irradiation experiments that will validate the data base.

Original language	English
Pages (from-to)	9-15
Number of pages	7
Journal	Journal of Nuclear Materials
Volume	417
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2011.05.023
State	Published - Oct 1 2011

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abstract = "The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion energy demonstration reactor blankets. This includes manufacturing technology, the as-fabricated and irradiates material database and joining technologies. The review indicated that the manufacturing technology, joining technology and database accumulation including irradiation data are ready for initial design activity, and also identifies various issues that remain to be solved for engineering design activity and qualification of the material for international fusion material irradiation facility (IFMIF) irradiation experiments that will validate the data base.",

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AU - Shiba, K.

AU - Möslang, A.

AU - Stoller, R. E.

AU - Lindau, R.

AU - Sokolov, M. A.

AU - Odette, G. R.

AU - Kurtz, R. J.

AU - Jitsukawa, S.

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Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket

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