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

被引：138

作者：

Tanigawa, H. ^{[1
]}

Shiba, K. ^{[1
]}

Moeslang, A. ^{[2
]}

Stoller, R. E. ^{[3
]}

Lindau, R. ^{[2
]}

Sokolov, M. A. ^{[3
]}

Odette, G. R. ^{[4
]}

Kurtz, R. J. ^{[5
]}

Jitsukawa, S. ^{[1
]}

机构：

[1] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan

[2] Forschungszentrum Karlsruhe, Inst Mat Forsch, D-76021 Karlsruhe, Germany

[3] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[4] Univ Calif Santa Barbara, Santa Barbara, CA 93106 USA

[5] Pacific NW Natl Lab, Richland, WA 99352 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2011年 / 417卷 / 1-3期

关键词：

CYCLE FATIGUE PROPERTIES; MECHANICAL-PROPERTIES; MARTENSITIC STEELS; TENSILE PROPERTIES; MICROSTRUCTURAL EVOLUTION; FERRITIC STEELS; IRRADIATION; HELIUM; F82H; EMBRITTLEMENT;

D O I：

10.1016/j.jnucmat.2011.05.023

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

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. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：9 / 15

页数：7

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