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

H. Tanigawa; T. Hirose; K. Shiba; R. Kasada; E. Wakai; H. Serizawa; Y. Kawahito; S. Jitsukawa; A. Kimura; Y. Kohno; A. Kohyama; S. Katayama; H. Mori; K. Nishimoto; R. L. Klueh; M. A. Sokolov; R. E. Stoller; S. J. Zinkle

doi:10.1016/j.fusengdes.2008.07.024

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

H. Tanigawa, T. Hirose, K. Shiba, R. Kasada, E. Wakai, H. Serizawa, Y. Kawahito, S. Jitsukawa, A. Kimura, Y. Kohno, A. Kohyama, S. Katayama, H. Mori, K. Nishimoto, R. L. Klueh, M. A. Sokolov, R. E. Stoller, S. J. Zinkle

Advanced Nuclear Materials

Research output: Contribution to journal › Article › peer-review

85 Scopus citations

Abstract

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.

Original language	English
Pages (from-to)	1471-1476
Number of pages	6
Journal	Fusion Engineering and Design
Volume	83
Issue number	10-12
DOIs	https://doi.org/10.1016/j.fusengdes.2008.07.024
State	Published - Dec 2008

Keywords

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

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2008.07.024

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Tanigawa, H., Hirose, T., Shiba, K., Kasada, R., Wakai, E., Serizawa, H., Kawahito, Y., Jitsukawa, S., Kimura, A., Kohno, Y., Kohyama, A., Katayama, S., Mori, H., Nishimoto, K., Klueh, R. L., Sokolov, M. A., Stoller, R. E., & Zinkle, S. J. (2008). Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules. Fusion Engineering and Design, 83(10-12), 1471-1476. https://doi.org/10.1016/j.fusengdes.2008.07.024

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title = "Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules",

abstract = "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.",

keywords = "F82H, Fabrication, HAZ, Irradiation effect, Over-tempered HAZ, RAFM, TBM, WCSB, Weld",

author = "H. Tanigawa and T. Hirose and K. Shiba and R. Kasada and E. Wakai and H. Serizawa and Y. Kawahito and S. Jitsukawa and A. Kimura and Y. Kohno and A. Kohyama and S. Katayama and H. Mori and K. Nishimoto and Klueh, {R. L.} and Sokolov, {M. A.} and Stoller, {R. E.} and Zinkle, {S. J.}",

year = "2008",

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doi = "10.1016/j.fusengdes.2008.07.024",

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Tanigawa, H, Hirose, T, Shiba, K, Kasada, R, Wakai, E, Serizawa, H, Kawahito, Y, Jitsukawa, S, Kimura, A, Kohno, Y, Kohyama, A, Katayama, S, Mori, H, Nishimoto, K, Klueh, RL, Sokolov, MA, Stoller, RE & Zinkle, SJ 2008, 'Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules', Fusion Engineering and Design, vol. 83, no. 10-12, pp. 1471-1476. https://doi.org/10.1016/j.fusengdes.2008.07.024

TY - JOUR

T1 - Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

AU - Tanigawa, H.

AU - Hirose, T.

AU - Shiba, K.

AU - Kasada, R.

AU - Wakai, E.

AU - Serizawa, H.

AU - Kawahito, Y.

AU - Jitsukawa, S.

AU - Kimura, A.

AU - Kohno, Y.

AU - Kohyama, A.

AU - Katayama, S.

AU - Mori, H.

AU - Nishimoto, K.

AU - Klueh, R. L.

AU - Sokolov, M. A.

AU - Stoller, R. E.

AU - Zinkle, S. J.

PY - 2008/12

Y1 - 2008/12

N2 - 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.

AB - 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.

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KW - Fabrication

KW - HAZ

KW - Irradiation effect

KW - Over-tempered HAZ

KW - RAFM

KW - TBM

KW - WCSB

KW - Weld

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M3 - Article

AN - SCOPUS:56949085715

SN - 0920-3796

VL - 83

SP - 1471

EP - 1476

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 10-12

ER -

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

Abstract

Keywords

UN SDGs

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