Recent progress in US-Japan collaborative research on ferritic steels R&D

Akihiko Kimura; Ryuta Kasada; Akira Kohyama; Hiroyasu Tanigawa; Takanori Hirose; Kiyoyuki Shiba; Shiro Jitsukawa; Satoshi Ohtsuka; Shigeharu Ukai; M. A. Sokolov; R. L. Klueh; Takuya Yamamoto; G. R. Odette

doi:10.1016/j.jnucmat.2007.03.013

Recent progress in US-Japan collaborative research on ferritic steels R&D

Akihiko Kimura, Ryuta Kasada, Akira Kohyama, Hiroyasu Tanigawa, Takanori Hirose, Kiyoyuki Shiba, Shiro Jitsukawa, Satoshi Ohtsuka, Shigeharu Ukai, M. A. Sokolov, R. L. Klueh, Takuya Yamamoto, G. R. Odette

Advanced Nuclear Materials

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

86 Scopus citations

Abstract

The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M₂₃C₆ carbides precipitation along lath block and packet boundaries, while that of JLF-1 is due to only the hardening effect. Dimensional change measurement during in-pile creep tests revealed the creep strain of F82H was limited at 300 °C. Performance of the weld bond under neutron irradiation will be critical to determine the life time of blanket structural components. Application of the ODS steels, which are resistant to corrosion in supercritical pressurized water, to the water-cooled blanket is essential to increase thermal efficiency of the blanket systems beyond DEMO. The coupling of RAFS and ODS steel could be effective to realize a highly efficient fusion blanket.

Original language	English
Pages (from-to)	60-67
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	367-370 A
Issue number	SPEC. ISS.
DOIs	https://doi.org/10.1016/j.jnucmat.2007.03.013
State	Published - Aug 1 2007

Funding

A part of this work is supported by US–Japan collaborative researches, DOE/JAERI and DOE/MEXT for the irradiation experiment, and by METI for the ODS steel R&D.

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10.1016/j.jnucmat.2007.03.013

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title = "Recent progress in US-Japan collaborative research on ferritic steels R&D",

abstract = "The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M23C6 carbides precipitation along lath block and packet boundaries, while that of JLF-1 is due to only the hardening effect. Dimensional change measurement during in-pile creep tests revealed the creep strain of F82H was limited at 300 °C. Performance of the weld bond under neutron irradiation will be critical to determine the life time of blanket structural components. Application of the ODS steels, which are resistant to corrosion in supercritical pressurized water, to the water-cooled blanket is essential to increase thermal efficiency of the blanket systems beyond DEMO. The coupling of RAFS and ODS steel could be effective to realize a highly efficient fusion blanket.",

author = "Akihiko Kimura and Ryuta Kasada and Akira Kohyama and Hiroyasu Tanigawa and Takanori Hirose and Kiyoyuki Shiba and Shiro Jitsukawa and Satoshi Ohtsuka and Shigeharu Ukai and Sokolov, {M. A.} and Klueh, {R. L.} and Takuya Yamamoto and Odette, {G. R.}",

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doi = "10.1016/j.jnucmat.2007.03.013",

language = "English",

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AU - Kimura, Akihiko

AU - Kasada, Ryuta

AU - Kohyama, Akira

AU - Tanigawa, Hiroyasu

AU - Hirose, Takanori

AU - Shiba, Kiyoyuki

AU - Jitsukawa, Shiro

AU - Ohtsuka, Satoshi

AU - Ukai, Shigeharu

AU - Sokolov, M. A.

AU - Klueh, R. L.

AU - Yamamoto, Takuya

AU - Odette, G. R.

PY - 2007/8/1

Y1 - 2007/8/1

N2 - The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M23C6 carbides precipitation along lath block and packet boundaries, while that of JLF-1 is due to only the hardening effect. Dimensional change measurement during in-pile creep tests revealed the creep strain of F82H was limited at 300 °C. Performance of the weld bond under neutron irradiation will be critical to determine the life time of blanket structural components. Application of the ODS steels, which are resistant to corrosion in supercritical pressurized water, to the water-cooled blanket is essential to increase thermal efficiency of the blanket systems beyond DEMO. The coupling of RAFS and ODS steel could be effective to realize a highly efficient fusion blanket.

AB - The mechanisms of irradiation embrittlement of two Japanese RAFSs were different from each other. The larger DBTT shift observed in F82H is interpreted by means of both hardening effects and a reduction of cleavage fracture stress by M23C6 carbides precipitation along lath block and packet boundaries, while that of JLF-1 is due to only the hardening effect. Dimensional change measurement during in-pile creep tests revealed the creep strain of F82H was limited at 300 °C. Performance of the weld bond under neutron irradiation will be critical to determine the life time of blanket structural components. Application of the ODS steels, which are resistant to corrosion in supercritical pressurized water, to the water-cooled blanket is essential to increase thermal efficiency of the blanket systems beyond DEMO. The coupling of RAFS and ODS steel could be effective to realize a highly efficient fusion blanket.

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SPEC. ISS.

ER -

Recent progress in US-Japan collaborative research on ferritic steels R&D

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