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Journal Articles

Deuterium retention in tungsten coating layers irradiated with deuterium and carbon ions

Fukumoto, Masakatsu; Nakano, Tomohide; Ueda, Yoshio*; Itami, Kiyoshi; Kubo, Hirotaka

Journal of Nuclear Materials, 462, p.354 - 359, 2015/07

 Times Cited Count:2 Percentile:73.33(Materials Science, Multidisciplinary)

Journal Articles

Reactivity of plasma-sintered beryllium-titanium intermetallic compounds with water vapor

Kim, Jae-Hwan; Nakamichi, Masaru

Journal of Nuclear Materials, 455(1-3), p.26 - 30, 2014/12

 Times Cited Count:9 Percentile:29.24(Materials Science, Multidisciplinary)

Journal Articles

Evaluation of damage accumulation behavior and strength anisotropy of NITE SiC/SiC composites by acoustic emission, digital image correlation and electrical resistivity monitoring

Nozawa, Takashi; Ozawa, Kazumi; Asakura, Yuki*; Koyama, Akira*; Tanigawa, Hiroyasu

Journal of Nuclear Materials, 455(1-3), p.549 - 553, 2014/12

 Times Cited Count:9 Percentile:29.24(Materials Science, Multidisciplinary)

SiC/SiC composite is a promising candidate material of fusion DEMO reactor. This paper aims to identify its damage tolerance and strength anisotropy by various characterization techniques such as acoustic emission (AE) monitoring, electrical resistivity (ER) measurement, and digital image correlation (DIC). The AE results identified that damage accumulation initiated prior to the proportional limit stress (PLS) by both tensile and compressive loadings for 2D composites. The preliminary AE waveform analysis implied that this AE detect strength corresponds to initiation of micro-cracking but the stress-strain curve shows further linearity due to the strong interfacial friction. Then fiber sliding occurred near the PLS, followed by the non-linearlity of the curve. The preliminary tensile test results using a notched specimen also suggest notch insensitivity of the composites in any loading directions. The detailed failure mechanism will eventually be discussed with ER and DIC results.

Journal Articles

Effects of manufacturing process on impact properties and microstructures of ODS steels

Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Kaito, Takeji; Tanaka, Kenya

Journal of Nuclear Materials, 455(1-3), p.480 - 485, 2014/12

 Times Cited Count:9 Percentile:29.24(Materials Science, Multidisciplinary)

Oxide dispersion strengthened (ODS) steels are noticed as an advanced alloy durable to high-temperature and high-dose neutron irradiation environment. Japan Atomic Energy Agency, 9-12Cr-ODS martensite steels have been developed as the primary candidate material for fast reactor fuel cladding tube. They would be also good candidates for fusion reactor blanket material. In this work, two types of 11Cr-ODS steels were manufactured: pre-mix and full pre-alloy ODS steels. Tensile tests, creep tests, 1/3 sized Charpy impact tests and metallurgical observations were carried out on these steels. The impact properties of full pre-alloy ODS steel was shown to be much superior than that of pre-mix ODS steels. It was demonstrated that the full pre-alloy process noticeably improved the microstructure homogeneity (i.e. reduction of inclusions and pores). The ductility of full pre-alloy ODS steels were better than that of pre-mix ODS steels.

Journal Articles

Overview of plasma-material interaction experiments on EAST employing MAPES

Ding, F.*; Luo, G.-N.*; Pitts, R.*; Litnovsky, A.*; Gong, X.*; Ding, R.*; Mao, H.*; Zhou, H.*; Wampler, W. R.*; Stangeby, P. C.*; et al.

Journal of Nuclear Materials, 455(1-3), p.710 - 716, 2014/12

 Times Cited Count:20 Percentile:8.06(Materials Science, Multidisciplinary)

Journal Articles

Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

Kanai, Akihiko*; Kasada, Ryuta*; Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio; Konishi, Satoshi*

Journal of Nuclear Materials, 455(1-3), p.431 - 435, 2014/12

 Times Cited Count:0 Percentile:100(Materials Science, Multidisciplinary)

Journal Articles

Properties of tritium/helium release from hot isostatic pressed beryllium of various trademarks

Chekushina, L.*; Dyussambayev, D.*; Shaimerdenov, A.*; Tsuchiya, Kunihiko; Takeuchi, Tomoaki; Kawamura, Hiroshi; Kulsartov, T.*

Journal of Nuclear Materials, 452(1-3), p.41 - 45, 2014/09

 Times Cited Count:1 Percentile:91.07(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of advanced neutron multipliers for DEMO blankets

Nakamichi, Masaru; Kim, Jae-Hwan

Fusion Science and Technology, 66, p.157 - 162, 2014/08

 Times Cited Count:1 Percentile:87.72(Nuclear Science & Technology)

Journal Articles

Honeycomb Palladium catalyst for the oxidation of tritiated hydrocarbons produced in tritium facilities

Iwai, Yasunori; Sato, Katsumi; Yamanishi, Toshihiko

Fusion Science and Technology, 66(1), p.214 - 220, 2014/07

 Times Cited Count:4 Percentile:58.26(Nuclear Science & Technology)

We have developed a honeycomb Pd catalyst applicable for the oxidation of the tritiated hydrocarbons. In this study, honeycomb Pd catalysts of three different densities, 2, 5 and 10 g/L, were prepared to investigate the effect of density on reaction rate. Tritiated methane was selected as a typical hydrocarbon. Overall reaction rate constant for tritiated methane oxidation on honeycomb Pd catalyst were determined with a flow-through system as a function of space velocity from 1000 to 6300 h$$^{-1}$$, methane concentration in carrier from 0.004 to 100 ppm, temperature of catalyst from 322 to 673 K. The density of palladium deposited on the base material had little effect on reaction rate for tritiated methane oxidation. The overall reaction rate constant was proportional to the space velocity. The overall reaction rate constant was independent on the methane concentration when it was less than 10 ppm.

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.

Fusion Science and Technology, 66(1), p.46 - 56, 2014/07

 Times Cited Count:4 Percentile:58.26(Nuclear Science & Technology)

Oral presentation

Tensile deformation behavior of plain-woven Tyranno-SA3 CVI-composites at elevated temperatures

Ozawa, Kazumi; Nozawa, Takashi; Toyoshima, Kazuoki*; Tanigawa, Hiroyasu; Hinoki, Tatsuya*

no journal, , 

An advanced SiC/SiC composite is a promising candidate material for fusion DEMO blanket. Current study preliminarily aims to examine tensile deformation behavior of unirradiated advanced SiC/SiC composites tested at high temperatures. In rupture tests being concurrently conducted at 1000$$^{circ}$$C in vaccum, it was revealed that the plain-woven CVI-SiC matrix composite reinforced with Tyranno-SA3 fibers did not fail at 174 MPa (equivalent to 130% of PLS at 1000$$^{circ}$$C) for 1986 hours. Presently there was no negative sign of the notch effects, implying their good rupture property at certain conditions of concern.

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