Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

被引：80

作者：

Tanigawa, H. ^{[1
]}

Hirose, T. ^{[1
]}

Shiba, K. ^{[1
]}

Kasada, B. R. ^{[2
]}

Wakaia, E. ^{[1
]}

Serizawa, H. ^{[3
]}

Kawahito, Y. ^{[3
]}

Jitsukawa, S. ^{[1
]}

Kimura, A. ^{[2
]}

Kohno, Y. ^{[4
]}

Kohyama, A. ^{[2
]}

Katayama, S. ^{[3
]}

Mori, H. ^{[5
]}

Nishimoto, K. ^{[5
]}

Klueh, R. L. ^{[6
]}

Sokolov, M. A. ^{[6
]}

Stoller, R. E. ^{[6
]}

Zinkle, S. J. ^{[6
]}

机构：

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

[2] Kyoto Univ, Inst Adv Energy, Kyoto 6110011, Japan

[3] Osaka Univ, Joining & Welding Res Inst, Osaka 5670047, Japan

[4] Muroran Inst Technol, Dept Mat Sci & Engn, Muroran, Hokkaido 0508585, Japan

[5] Osaka Univ, Div Mat & Mfg Sci, Suita, Osaka 5650871, Japan

[6] Oak Ridge Natl Lab, Div Mat Sci & Technol, Oak Ridge, TN 37831 USA

来源：

FUSION ENGINEERING AND DESIGN | 2008年 / 83卷 / 10-12期

关键词：

RAFM; F82H; TBM; WCSB; Fabrication; Weld; HAZ; Over-tempered HAZ; Irradiation effect;

D O I：

10.1016/j.fusengdes.2008.07.024

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. The RAFM F82H was developed in Japan with emphasis on high-temperature properties and weldability. Extensive irradiation studies have conducted on F82H, and it has the most extensive available database of irradiated and unirradiated properties of all RAFMs. The objective of this paper is to review the R&D status of F82H and to identify the key technical issues for the fabrication of an ITER test blanket module (TBM) suggested from the recent research achievements in Japan. This work clarified that the primary issues with F82H involve welding techniques and the mechanical properties of weld joints. This is the result of the distinctive nature of the joint caused by the phase transformation that occurs in the weld joint during cooling, and its impact on the design of a TBM will be discussed. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：1471 / 1476

页数：6

共 28 条

[1] Effects of thermal aging on the mechanical behavior of F82H weldments [J].

Alamo, A ;

Castaing, A ;

Fontes, A ;

Wident, P .

JOURNAL OF NUCLEAR MATERIALS, 2000, 283 :1192-1195

[2] Overview of design and R&D of test blankets in Japan [J].

Enoeda, M ;

Akiba, M ;

Tanaka, S ;

Shimizu, A ;

Hasegawa, A ;

Konishi, S ;

Kimura, A ;

Kohyama, A ;

Sagara, A ;

Muroga, T .

FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :415-424

[3] Type IV cracking in ferritic power plant steels [J].

Francis, J. A. ;

Mazur, W. ;

Bhadeshia, H. K. D. H. .

MATERIALS SCIENCE AND TECHNOLOGY, 2006, 22 (12) :1387-1395

[4] Deformation microstructure of a reduced-activation ferritigmartensitic steel irradiated in HFIR [J].

Hashimoto, N ;

Klueh, RL ;

Ando, M ;

Tanigawa, H ;

Sawai, T ;

Shiba, K .

FUSION SCIENCE AND TECHNOLOGY, 2003, 44 (02) :490-494

[5] MECHANICAL-PROPERTIES OF WELDED-JOINTS OF THE REDUCED-ACTIVATION FERRITIC STEEL - 8-PERCENT CR-2-PERCENT W-0.2-PERCENT V-0.04-PERCENT TA-FE [J].

HAYAKAWA, H ;

YOSHITAKE, A ;

TAMURA, M ;

NATSUME, S ;

GOTOH, A ;

HISHINUMA, A .

JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :693-696

[6]

HIROSE T, 2005, P 13 INT WORKSH CER

[7] Recent results of the reduced activation ferritic/martensitic steel development [J].

Jitsukawa, S ;

Kimura, A ;

Kohyama, A ;

Klueh, RL ;

Tavassoli, AA ;

van der Schaaf, B ;

Odette, GR ;

Rensman, JW ;

Victoria, M ;

Petersen, C .

JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :39-46

[8] Elucidation of high-power fibre laser welding phenomena of stainless steel and effect of factors on weld geometry [J].

Kawahito, Yousuke ;

Mizutani, Masami ;

Katayama, Seiji .

JOURNAL OF PHYSICS D-APPLIED PHYSICS, 2007, 40 (19) :5854-5859

[9] EFFECTS OF SMALL CHANGES IN ALLOY COMPOSITION ON THE MECHANICAL-PROPERTIES OF LOW ACTIVATION 9-PERCENT CR-2-PERCENT W STEEL [J].

KAYANO, H ;

KIMURA, A ;

NARUI, M ;

KIKUCHI, T ;

OHTA, S .

JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :671-674

[10] Effects of surface morphology on fatigue behavior of reduced activation ferritic/martensitic steel [J].

Kim, S. W. ;

Tanigawa, H. ;

Hirose, T. ;

Shiba, K. ;

Kohyama, A. .

JOURNAL OF NUCLEAR MATERIALS, 2007, 367 :568-574

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