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Your search keyword '"Muroga, Takeo"' showing total 137 results
Start Over Author "Muroga, Takeo" Journal journal of nuclear materials
137 results on '"Muroga, Takeo"'

25. Characterization and qualification of neutron radiation effects – Summary of Japan-USA Joint Projects for 40 years –

Author

MUROGA, Takeo, HATANO, Y., CLARK, D., and KATOH, Y.

Subjects
Irradiation correlation, Neutron radiation effects, Nuclear and High Energy Physics, Nuclear Energy and Engineering, Low activation materials, General Materials Science, Transmutation
Abstract

The Joint Projects under the Japan-USA Fusion Cooperation Program started in 1981 and has continued for more than 40 years. In the Joint Projects, although a wide range of fusion materials and engineering issues were covered, neutron radiation effects on fusion reactor materials have always been the major research emphases, and the neutron irradiation facilities in the US were jointly used by Japanese and US researchers. Japanese test facilities including neutron and charged particle irradiation facilities were complementarily used.The initial focus of the Joint Projects was on fundamental fusion neutron radiation effects and irradiation correlation. Systematic comparison of fission and fusion radiation effects in comparable damage levels and the effects of transmutation-induced helium were investigated. The collaboration was then focused on the effect of dynamic irradiation effects in variable conditions. In addition to the relatively fundamental studies, the Joint Projects contributed largely to development of candidate materials such as RAFM steels, vanadium alloys, SiC/SiC composites, and tungsten alloys, through a mechanism-oriented approach. The Joint Projects also covered issues specific to materials application to fusion blankets and plasma-facing components, including neutron radiation effects such as tritium retention and permeation of neutron-irradiated plasma-facing materials. Various irradiation technologies were developed and applied to the irradiation experiments, including those for in-situ testing.Considering that high energy neutron sources, such as A-FNS and IFMIF-DONES, now have high viability, the research supporting the neutron source programs is essential. The knowledge obtained through the Joint Projects is valuable and should be advanced for this purpose. To this end, it is of urgent necessity to launch an international scientific program accumulating knowledge of fusion neutron radiation effects, including their fundamental aspects.

Published
2022

30. Interfacial characterization of dissimilar-metals bonding between vanadium alloy and Hastelloy X alloy by explosive welding

Author

Jiang, Shaoning, primary, Shen, Jingjie, additional, Nagasaka, Takuya, additional, Muroga, Takeo, additional, Sagara, Akio, additional, Ohnuki, Somei, additional, Hokamoto, Kazuyuki, additional, Tanaka, Shigeru, additional, Inao, Daisuke, additional, Morizono, Yasuhiro, additional, Kasada, Ryuta, additional, and Zheng, Pengfei, additional

Published
2020
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42. Fluoridation and oxidation characteristics of JLF-1 and NIFS HEAT-2 low-activation structural materials

Author

Nagasaka, Takuya, Kondo, Masatoshi, Muroga, Takeo, Hatori, Nobuaki, Tsunoda, Ken, Sagara, Akio, Motojima, Osamu, Suzuki, Akihiro, and Terai, Takayuki

Subjects
Nuclear and High Energy Physics, Structural material, Moisture, FLiBe, Corrosion, chemistry.chemical_compound, Nuclear Energy and Engineering, chemistry, Impurity, Oxidizing agent, General Materials Science, Molten salt, Fluoride, Nuclear chemistry
Abstract

Fluoridation and oxidation of JLF-1 (Fe–9Cr–2W–0.1C) and NIFS-HEAT-2 (V–4Cr–4Ti) were examined under various corrosion conditions, such as Flibe (2LiF + BeF2) molten salt at 823 K for 2003 h, H2O–47%HF solution at RT for 2 min, and He–(0–1%)HF gas mixture containing moisture and O2 gas impurities at 823 K for 2.5–100 h. Oxidation dominated fluoridation under all test conditions, even when the fluoridation agent, the F atoms in HF, was 16× more plentiful than the oxidation agent, O atoms in H2O, and O2. Corrosion products were mainly considered as Cr2O3, while fluoride was indicated in a very limited surface region. JLF-1 exhibited better corrosion resistance in He–HF gas mixture tests than NIFS-HEAT-2.

Published
2009

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