Fukumoto, Masakatsu; Nakano, Tomohide; Ueda, Yoshio*; Itami, Kiyoshi; Kubo, Hirotaka
Journal of Nuclear Materials, 462, p.354 - 359, 2015/07
Kim, Jae-Hwan; Nakamichi, Masaru
Journal of Nuclear Materials, 455(1-3), p.26 - 30, 2014/12
Nozawa, Takashi; Ozawa, Kazumi; Asakura, Yuki*; Koyama, Akira*; Tanigawa, Hiroyasu
Journal of Nuclear Materials, 455(1-3), p.549 - 553, 2014/12
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.
Tanno, Takashi; Otsuka, Satoshi; Yano, Yasuhide; Kaito, Takeji; Tanaka, Kenya
Journal of Nuclear Materials, 455(1-3), p.480 - 485, 2014/12
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.
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
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
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
no abstracts in English
Nakamichi, Masaru; Kim, Jae-Hwan
Fusion Science and Technology, 66, p.157 - 162, 2014/08
Iwai, Yasunori; Sato, Katsumi; Yamanishi, Toshihiko
Fusion Science and Technology, 66(1), p.214 - 220, 2014/07
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, 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.
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
Sugimoto, Masayoshi; Knaster, J.*; Arbeiter, F.*; Cara, P.*; Favuzza, P.*; Furukawa, Tomohiro; Gioacchino, M.*; Groeschel, F.*; Heidinger, R.*; Ibarra, A.*; et al.
no journal, ,
Under the framework of the Broader Approach agreement between Japan and EURATOM the concept of the International Fusion Materials Irradiation Facility (IFMIF) to provide the intense neutron irradiation test facility for developing the fusion reactor materials has been evolved since 2007, through the activities to prepare the engineering design documents for IFMIF with the associated R&D of prototypical components, named as IFMIF Engineering Validation and Engineering Design Activities (EVEDA) project. Recently the Intermediate IFMIF Engineering Design Report for IFMIF (IIEDR) was delivered in July 2013, which is supported by the major outcomes of the validation activities of the prototypical components: Linear IFMIF Prototype Accelerator, EVEDA Lithium Test Loop, High Flux Test Module capsule, etc. In this article, the progresses of the IIEDR and validation tests and also the outcomes to be achieved till mid 2017, the completion time of IFMIF/EVEDA, will be comprehensively overviewed.
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 1000C 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 1000C) for 1986 hours. Presently there was no negative sign of the notch effects, implying their good rupture property at certain conditions of concern.