Current status and future R&D for reduced-activation ferritic/martensitic steels

被引：217

作者：

Hishinuma, A ^{[1
]}

Kohyama, A

Klueh, RL

Gelles, DS

Dietz, W

Ehrlich, K

机构：

[1] Japan Atom Energy Res Inst, Tokai Estab, Dept Mat Sci & Engn, Tokai, Ibaraki 31911, Japan

[2] Kyoto Univ, Inst Adv Energy, Uji, Kyoto 611, Japan

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

[4] Pacific NW Lab, Richland, WA 99352 USA

[5] EC DGXII Fus Program, Brussels, Belgium

[6] Forschungszentrum Karlsruhe, Inst Mat Forsch 1, D-76021 Karlsruhe, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 1998年 / 258卷

关键词：

D O I：

10.1016/S0022-3115(98)00395-X

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

International research and development programs on reduced-activation ferritic/martensitic steels, the primary candidate-alloys for a DEMO fusion reactor and beyond, are briefly summarized, along with some information on conventional steels. An International Energy Agency (IEA) collaborative test program to determine the feasibility of reduced-activation ferritic/martensitic steels for fusion is in progress and will be completed within this century. Baseline properties including typical irradiation behavior for Fe-(7-9)%Cr reduced-activation ferritic steels are shown. Most of the data are for a heat of modified F82H steel, purchased for the][EA program. Experimental plans to explore possible problems and solutions for fusion devices using ferromagnetic materials are introduced. The preliminary results show that it should be possible to use a ferromagnetic vacuum vessel in tokamak devices. (C) 1998 Published by Elsevier Science B.V. All rights reserved.

引用

页码：193 / 204

页数：12

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