Effects of hydrogen on the mechanical properties of oxide dispersion strengthening steels

Lee, J.S; Kimura, Akihiko; Ukai, Shigeharu; Fujiwara, Masayuki

doi:10.1016/j.jnucmat.2004.04.035

Cited by 39 publications

(21 citation statements)

References 6 publications

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“…The weight gain of the RAFS, JLF-1, attained 800 g/m 2 for 200 h. The 9% Cr-ODS steel of the first generation of ODS steels is almost the same as that of a ferritic/martensitic steel. In comparison with the first generation of the ODS steels, the second generation of high-Cr ODS steels (>14% Cr) showed a high corrosion resistance better than an austenitic stainless steel (SUS316) [27,28]. Furthermore, an increase of chromium and an addition of aluminum at the same time resulted in further suppression of corrosion.…”

Section: Super-critical Pressurized Watermentioning

confidence: 99%

Ferritic steel-blanket systems integration R&D—Compatibility assessment

Kimura¹,

Kasada²,

Konishi³

et al. 2006

Fusion Engineering and Design

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Section: Super-critical Pressurized Watermentioning

confidence: 99%

Ferritic steel-blanket systems integration R&D—Compatibility assessment

Kimura¹,

Kasada²,

Konishi³

et al. 2006

Fusion Engineering and Design

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“…Hydrogen charging caused a reduction of tensile elongation, which became large with increasing charging current density or hydrogen concentration. 59) The hydrogen concentrations in 14Cr-ODS and 9Cr-2W steel, which were measured by TDS analysis, were shown in Fig. 12 as a function of cathodic current density as well as the calculation results following to McNabb & Foster trapping model.…”

Section: Hydrogen Embrittlementmentioning

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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“…It is well known that the corrosion resistance in high-temperature water diminishes significantly with decreasing chromium concentration below 13% [6][7][8][9][10][11][12]. In order to improve corrosion resistance in super critical pressurized water (SCPW), high-Cr-ODS steels have been developed [7][8][9][10][11][12][13]. However irradiation embrittlement caused by the Fe-Cr phase decomposition under neutron irradiation is a critical issue for high-Cr steels.…”

Section: Introductionmentioning

confidence: 99%