Progress of advanced material tokamak experiment (AMTEX) program on JFT-2M

Kimura, Hiroyuki; Satō, Masayasu; Kawashima, H.; Isei, N.; Tsuzuki, K.; Ogawa, Hideyuki; Ogawa, T.; Miura, Y.; Yamamoto, Masahiro; Shibata, T.; Akiyama, T.; Miyachi, K.

doi:10.1016/s0920-3796(01)00362-3

Cited by 19 publications

(9 citation statements)

References 9 publications

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“…Recent operation tests of the JFT-2M facility with F82H plates in it showed no deteriorating effects on plasma but reduction of the toroidal field ripple. 21) Since high-temperature strength of the RAF/M steels is limited, many efforts have been made to increase the strength for highly thermal-efficient blanket system. One of the effective methods is to design the RAF/M steel-blanket in combination with oxide dispersion strengthening (ODS) ferritic/martensitic steels, which have a remarkably higher strength than RAF/M steels.…”

Section: Introductionmentioning

confidence: 99%

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Kimura

2005

Mater. Trans.

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Reduced-activation ferritic/martensitic (RAF/M) steels have been considered to be the prime candidate for the fusion blanket structural material. The irradiation data obtained up to now indicates rather high feasibility of the steels for application to fusion reactors because of their high resistance to degradation of material performance caused by both the irradiation-induced displacement damage and transmutation helium atoms. The martensitic structure of RAF/M steels consists of a large number of lattice defects before the irradiation, which strongly retards the formation of displacement damage through absorption and annihilation of the point defects generated by irradiation. Transmutation helium can be also trapped at those defects in the martensitic structure so that the growth of helium bubbles at grain boundaries is suppressed. The major properties of the steels are well within our knowledge, and processing technologies are mostly developed for fusion application. RAF/M steels are now certainly ready to proceed to the next stage, that is, the construction of International Thermo-nuclear Experimental Reactor Test Blanket Modules (ITER-TBM).Oxide dispersion strengthening (ODS) steels have been developed for higher thermal efficiency of fusion power plants. Recent irradiation experiments indicated that the steels were quite highly resistant to neutron irradiation embrittlement, showing hardening accompanied by no loss of ductility. High-Cr ODS steels whose chromium concentration was in the range from 14 to 19 mass% showed high resistance to corrosion in supercritical pressurized water. It is shown that the 14Cr-ODS steel is susceptible to neither hydrogen nor helium embrittlement.A combined utilization of ODS steels with RAF/M steels will be effective to realize fusion power early at a reasonable thermal efficiency.

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Section: Introductionmentioning

confidence: 99%

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Kimura

2005

Mater. Trans.

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“…The samples are cut from the F82H plates used in the JFT-2 M tokamak at JAERI (now JAEA) [10]. The stainless steel sample is used as a comparative reference.…”

Section: Methodsmentioning

confidence: 99%

First Wall Particle Flux Measurements by an F82H Permeation Probe in QUEST

Zhou

Hirooka

Zushi

et al. 2014

Plasma and Fusion Research

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First wall particle flux measurements in the QUEST spherical tokamak have been conducted, using a permeation probe that employs a first wall candidate ferritic steel alloy F82H as the membrane and also SUS304 as a comparative reference membrane. Permeation measurements have been done during the conditioning steadystate discharges heated with 2.45 GHz and 8.2 GHz ECR. Diffusion and recombination coefficients measured in a laboratory-scale plasma device: VEHICLE-1 are used to interpret the results from the permeation probe measurements in QUEST. These permeation membranes have been analyzed with XPS to evaluate the effects of surface impurities.

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“…The influence of ferromagnetism on plasma operation has often been a concern. Recent operation tests of the JFT-2M facility with F82H plates in it show no deteriorating effects on the plasma but a reduction in the toroidal field ripple [6].…”

Section: Fabrication Technologies and Ferromagnetismmentioning

confidence: 98%

Recent progress in reduced activation ferritic steels R&D in Japan

Kimura

Sawai²,

Shiba³

et al. 2003

Nucl. Fusion

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The Japanese RAFSs R&D road map toward DEMO is shown. Important steps include high-dose irradiation by fission reactors, such as HFIR in ORNL, irradiation tests by 14 MeV neutrons in IFMIF and application to ITER test blanket modules to provide an adequate database of RAFS for the design of DEMO. Current status of RAFS development is also introduced. The major properties of concern are well within our knowledge and process technologies are mostly ready for fusion application. The RAFSs are now certainly ready to proceed to the next stage. Material database is already in hand and further progress is anticipated for the design of ITER test blanket. Oxide Dispersion strengthening (ODS) steels are quite promising for high temperature operation of the blanket system with potential improvements in radiation resistance of mechanical performances and of corrosion.

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Progress of advanced material tokamak experiment (AMTEX) program on JFT-2M

Cited by 19 publications

References 9 publications

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

Current Status of Reduced-Activation Ferritic/Martensitic Steels R&D for Fusion Energy

First Wall Particle Flux Measurements by an F82H Permeation Probe in QUEST

Recent progress in reduced activation ferritic steels R&D in Japan

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