Metallurgical study on corrosion of RAFM steel JLF-1 in Pb-Li alloys with various Li concentrations

Kondo, Masatoshi; Ishii, Masaomi; Hishinuma, Yoshimitsu; Tanaka, Teruya; Nozawa, Takashi; Muroga, T.

doi:10.1016/j.fusengdes.2017.04.058

Cited by 23 publications

(4 citation statements)

References 26 publications

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“…The development of nuclear fusion reactors requires a breakthrough in materials technology. Reduced activation ferritic/martensitic (RAFM) steels are currently recognised as the leading candidates for the structural material role in nuclear reactors, because of their dependable industrial bases and superior swelling resistance [1]. Over several decades, many researchers have attempted to improve the mechanical properties of RAFM steels and to confirm their feasibility for reactor blankets.…”

Section: Introductionmentioning

confidence: 99%

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Qiu

Zhan

et al. 2018

Materials Science and Technology

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This study investigates the inclusions, microstructure, tensile properties, and impact toughness of reduced activation ferritic/martensitic (RAFM) steels with different Y contents (0.006, 0.034 and 0.071 wt-%). Owing to the pinning of the grain boundary to the Y inclusions (which refines the original austenite grain size) and an existing Fe–Cr–Ta–Y–S–O phase, the tensile strength at both room and high temperatures increased with increasing Y content (below 0.071%). Increasing the Y content to 0.034 wt-% decreased the ductile-to-brittle transition temperature (DBTT). However, when the Y content reached 0.071 wt-%, the DBTT increased as the Y precipitated into blocky yttrium-rich inclusions. The microstructure, tensile properties, and impact toughness of the RAFM steel were optimised at a Y content of approximately 0.034 wt-%.

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Section: Introductionmentioning

confidence: 99%

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Qiu

Zhan

et al. 2018

Materials Science and Technology

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“…Obviously, DBTT increases significantly with increasing grain size. Hence, a small grain size (i.e., 10-20 µm) is generally expected for RAFM steels [11][12][13][14][15][16].…”

Section: Creep Direction Creep Directionmentioning

confidence: 99%

“…The tensile properties of the material are comparable to those of commercial 9Cr-1MoVNb heat-resistant steels. Since then, many countries have developed different types of RAFM steels, such as the F82H [11] and JLF series steels [12] in Japan, the EUROFER97 steel [13] in Europe, the China low activation martensitic (CLAM) steel [14] in China [12][13], the INRAFM steel in India [15], and the ARAA steel in South Korea [16]. So far, RAFM steels have achieved industrial production.…”

Section: Introductionmentioning

confidence: 99%

Strengthening mechanisms of reduced activation ferritic/martensitic steels: A review

Zhou

Shen

Jia

2021

Int J Miner Metall Mater

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This review summarizes the strengthening mechanisms of reduced activation ferritic/martensitic (RAFM) steels. High-angle grain boundaries, subgrain boundaries, nano-sized M 23 C 6 , and MX carbide precipitates effectively hinder dislocation motion and increase high-temperature strength. M 23 C 6 carbides are easily coarsened under high temperatures, thereby weakening their ability to block dislocations. Creep properties are improved through the reduction of M 23 C 6 carbides. Thus, the loss of strength must be compensated by other strengthening mechanisms. This review also outlines the recent progress in the development of RAFM steels. Oxide dispersion-strengthened steels prevent M 23 C 6 precipitation by reducing C content to increase creep life and introduce a high density of nano-sized oxide precipitates to offset the reduced strength. Severe plastic deformation methods can substantially refine subgrains and MX carbides in the steel. The thermal deformation strengthening of RAFM steels mainly relies on thermo-mechanical treatment to increase the MX carbide and subgrain boundaries. This procedure increases the creep life of TMT(thermo-mechanical treatment) 9Cr-1W-0.06Ta steel by ~20 times compared with those of F82H and Eurofer 97 steels under 550°C/260 MPa.

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“…Tech.) 41 Materials Hot laboratories (Tohoku U.) 77 Ion irradiation test facilities (Kyoto U./ Kyushu U.)…”

Section: Research Subjects Major Emphases Key Facilities In Nifs Exam...mentioning

confidence: 99%

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Muroga

Fukada

Hayashi

2019

Fusion Science and Technology

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This paper provides an overview of Japanese fusion engineering research activities focusing on those being carried out by NIFS and Japanese universities (Universities). NIFS is promoting the Fusion Engineering Research Project as one of the three research projects. The majority of the activity in the project is being carried out by collaboration with Universities. Utilizing core facilities installed in NIFS and the unique infrastructures of Universities, collaboration between NIFS and Universities is performed in superconducting magnet, liquid breeder blanket, advanced materials, high heat flux components, and tritium safety. NIFS also carries out international collaboration programs, such as Japan-China, Japan-USA, and IEA-based collaborations, promoting participation of University researchers. Responsibility division with QST, and contributions to ITER-BA and "Action Plan toward DEMO Development" are also reported.

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Metallurgical study on corrosion of RAFM steel JLF-1 in Pb-Li alloys with various Li concentrations

Cited by 23 publications

References 26 publications

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Strengthening mechanisms of reduced activation ferritic/martensitic steels: A review

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

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