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Journal Articles

$$^{155}$$Gd M$"o$ssbauer spectroscopic and powder X-ray diffraction study of CeO$$_{2}$$ - GdO$$_{1.5}$$ solid solution

Nakamura, Akio; Imai, Kazutaka*; Igawa, Naoki; Okamoto, Yoshihiro; Yamamoto, Etsuji; Matsukawa, Shiro*; Takahashi, Masashi*

Hyperfine Interactions, 207(1-3), p.67 - 71, 2012/03

 Times Cited Count:4 Percentile:87.16

Journal Articles

Effects of heat treatment and irradiation on mechanical properties in F82H steel doped with boron and nitrogen

Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo*; Sawai, Tomotsugu; Kitazawa, Sin-iti; Jitsukawa, Shiro

Journal of Nuclear Materials, 367-370(1), p.107 - 111, 2007/08

 Times Cited Count:6 Percentile:42.6(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Small specimen test technology of fracture toughness in structural material F82H steel for fusion nuclear reactors

Wakai, Eiichi; Otsuka, Hideo; Matsukawa, Shingo*; Ando, Masami; Jitsukawa, Shiro

JAEA-Technology 2006-019, 58 Pages, 2006/03

JAEA-Technology-2006-019.pdf:7.15MB

Small specimen test technology (SSTT) has been developed to investigate mechanical properties of nuclear materials. SSTT has been driven by limited availability of effective irradiation volumes in test reactors and accelerator-based neutron and charged particle sources, and it is very useful for the reduction of waste materials produced in nuclear engineering. In this study new bend test machines have been developed to obtain fracture behaviors of F82H steel for very small bend specimens of pre-cracked $$frac{t}{2}$$-$$frac{1}{3}$$CVN (Charpy V-notch) with 20 mm-length and DFMB (deformation and fracture mini bend specimen) with 9 mm-length and disk compact tension of 0.18DCT type, and fracture behaviors were examined to evaluate DBTT (ductile-brittle transition temperature) at temperatures from -180 to 250$$^{circ}$$C. The effect of specimen size on DBTT of F82H steel was also examined by using Charpy type specimens such as $$frac{t}{2}$$-CVN, $$frac{1}{3}$$CVN and $$frac{t}{2}$$-$$frac{1}{3}$$CVN. In this paper, it also provides the information of the specimens irradiated at 250$$^{circ}$$C and 350$$^{circ}$$C to about 2 dpa in the capsules of 04M-67A and 04M-68A of JMTR experiments.

Journal Articles

Mechanical properties of small size specimens of F82H steel

Wakai, Eiichi; Otsuka, Hideo*; Matsukawa, Shingo; Furuya, Kazuyuki*; Tanigawa, Hiroyasu; Oka, Keiichiro*; Onuki, Somei*; Yamamoto, Toshio*; Takada, Fumiki; Jitsukawa, Shiro

Fusion Engineering and Design, 81(8-14), p.1077 - 1084, 2006/02

 Times Cited Count:11 Percentile:60.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tempering treatment effect on mechanical properties of F82H steel doped with boron and nitrogen

Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo; Tanigawa, Hiroyasu; Sawai, Tomotsugu; Jitsukawa, Shiro; Onuki, Somei*

Materials Transactions, 46(8), p.1779 - 1782, 2005/08

 Times Cited Count:1 Percentile:16.31(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Heat treatment effects on microstructures and DBTT of F82H steel doped with boron and nitrogen

Okubo, Nariaki; Wakai, Eiichi; Matsukawa, Shingo*; Furuya, Kazuyuki; Tanigawa, Hiroyasu; Jitsukawa, Shiro

Materials Transactions, 46(2), p.193 - 195, 2005/02

 Times Cited Count:1 Percentile:16.31(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Post irradiation plastic properties of F82H derived from the instrumented tensile tests

Taguchi, Tomitsugu; Jitsukawa, Shiro; Sato, Michitaka*; Matsukawa, Shingo*; Wakai, Eiichi; Shiba, Kiyoyuki

Journal of Nuclear Materials, 335(3), p.457 - 461, 2004/12

 Times Cited Count:11 Percentile:58.63(Materials Science, Multidisciplinary)

F82H (Fe-8Cr-2W) and its variant doped with 2%Ni were irradiated up to 20 dpa at 300$$^{circ}$$C in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. Post irradiation tensile testing was performed at room temperature. During testing, the images of the specimens including the necked region were continuously recorded. Tests on cold worked material were also carried out for comparison. From the load-displacement curves and the strain distributions obtained from the images, flow stress levels and strain hardening behavior was evaluated. A preliminary constitutive equation for the plastic deformation of irradiated F82H is presented. The results suggest that the irradiation mainly causes defect-induced hardening while it did not strongly affect strain hardening at the same flow stress level for F82H irradiated at 300$$^{circ}$$C. The strain hardening of Ni doped specimens was, however, strongly affected by irradiation. Results provide basics to determine allowable stress levels at temperatures below 400$$^{circ}$$C.

Journal Articles

Extra radiation hardening and microstructural evolution in F82H by high-dose dual ion irradiation

Ando, Masami; Wakai, Eiichi; Sawai, Tomotsugu; Matsukawa, Shingo; Naito, Akira*; Jitsukawa, Shiro; Oka, Keiichiro*; Tanaka, Teruyuki*; Onuki, Somei*

JAERI-Review 2004-025, TIARA Annual Report 2003, p.159 - 161, 2004/11

The objectives of this study are to evaluate radiation hardening on ion-irradiated F82H up to 100 dpa and to examine the extra component of radiation hardening due to implanted helium atoms (up to $$sim$$3000 appmHe) in F82H under ratio of 0, 10, 100 appmHe/dpa.The ion-beam irradiation experiment was carried out at the TIARA facility of JAERI. Specimens were irradiated at 633 K by 10.5 MeV Fe ions with/without 1.05 MeV He ions. Micro-indentation tests were performed at loads to penetrate about 0.40 mm in the irradiated specimens using an UMIS-2000. The results are summarized as follows:1) As a result of the single irradiated F82H, the micro-hardness tended to increase about 30 dpa. 2) The extra radiation hardening was obviously caused by co-implanted helium atoms more than 1000 appm in F82H irradiated at 633 K. 3) In the dual-beam (100 appmHe/dpa) irradiated microstructure, nano-voids and fine defects were observed. It is suggested that the formation of nano-voids causes the extra radiation hardening by helium co-implantation.

Journal Articles

Mechanical property of F82H steel doped with boron and nitrogen

Wakai, Eiichi; Matsukawa, Shingo; Yamamoto, Toshio*; Kato, Yoshiaki; Takada, Fumiki; Sugimoto, Masayoshi; Jitsukawa, Shiro

Materials Transactions, 45(8), p.2641 - 2643, 2004/08

 Times Cited Count:6 Percentile:41.18(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

 Times Cited Count:2 Percentile:17.07(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

Journal Articles

Stress analysis of poloidal field coil support in JT-60U

Matsukawa, Makoto; *; Horiike, Hiroshi; Ninomiya, Hiromasa; Neyatani, Yuzuru; Ando, Toshiro; *

Nihon Genshiryoku Gakkai-Shi, 35(6), p.561 - 573, 1993/06

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

JT-60 operation results after its modification for higher plasma current with single null open divertor

; Horiike, Hiroshi; Neyatani, Yuzuru; Matsukawa, Makoto; Ando, Toshiro; Yoshino, Ryuji; Arai, Takashi; Ninomiya, Hiromasa; Yamamoto, Masahiro; ; et al.

Proc. of the 14th Symp. on Fusion Engineering,Vol. 1, p.177 - 180, 1992/00

no abstracts in English

Journal Articles

Design and development of JT-60 upgrade; Vacuum vessel and first wall

Horiike, Hiroshi; Ando, Toshiro; *; Matsukawa, Makoto; Neyatani, Yuzuru; Ninomiya, Hiromasa; Yamamoto, Masahiro

Fusion Engineering and Design, 16, p.285 - 292, 1991/00

 Times Cited Count:16 Percentile:83.04(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present status of JT-60 upgrade

Horiike, Hiroshi; Ando, Toshiro; ; *; Koizumi, Koichi; Matsukawa, Makoto; Neyatani, Yuzuru; Ninomiya, Hiromasa; Shimizu, Masatsugu; Yamamoto, Masahiro

1989 IEEE 13th Symp. on Fusion Engineering,Vol. 2, p.1049 - 1054, 1990/00

no abstracts in English

Journal Articles

JT-60 upgrade program

Kikuchi, Mitsuru; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; ; Koizumi, Koichi; Matsukawa, Makoto; ; et al.

Fusion Technology 1988, p.287 - 292, 1989/00

no abstracts in English

Journal Articles

JT-60U system design

Matsukawa, Makoto; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; Kikuchi, Mitsuru; ; Koizumi, Koichi; ; et al.

Fusion Technology 1988, p.293 - 297, 1989/00

no abstracts in English

Oral presentation

Laser driven ion acceleration experiment by high contrast high intensity laser J-KAREN system

Nishiuchi, Mamiko; Sakaki, Hironao; Sagisaka, Akito; Maeda, Shota; Pirozhkov, A. S.; Pikuz, T.; Faenov, A. Ya.*; Ogura, Koichi; Fukuda, Yuji; Matsukawa, Kenya*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurement of electron spectrum generated by irradiating thin-Foil target with Ultra-intense Ultra-short pulse laser

Maeda, Shota; Nishiuchi, Mamiko; Sakaki, Hironao; Sagisaka, Akito; Pirozhkov, A. S.; Pikuz, T.; Faenov, A. Ya.*; Ogura, Koichi; Fukuda, Yuji; Matsukawa, Kenya*; et al.

no journal, , 

In JAEA, the high energy ions generated by the interaction between Ultra-intense Ultra-Short pulse laser and thin-foil target is being studied. Irradiating condition must be optimized to generate higher energy ions while suppress the becoming gigantic of laser. It is necessary to know the physical phenomenon in plasma to determine the parameter to optimize from the information on the electron and neutron, X-rays, which are generated simultaneously with ion. In this study, in order to measure electron temperature accurately, an electron spectrometer was developed which have broad range (1-200 MeV). The detector is comprised of permanent magnets and a fluorescent plate, CCD camera. In the presentation, the result of the calibration experiment carried out using 4, 9, 12, 15 MeV quasi-monoenergetic electron beam in HIBMC will be reported. Moreover, response analysis method was inspected using PHITS which is particle transporting Monte Carlo simulation code, and will also report the result.

Oral presentation

Magnetic behavior and magnetic structure of CuO$$_{2}$$ ribbon system A$$_{2}$$Cu$$_{2}$$Mo$$_{3}$$O$$_{12}$$ (A=Rb, Cs)

Fujimura, Akio*; Yasui, Yukio*; Kono, Yohei*; Kittaka, Shunichiro*; Sakakibara, Toshiro*; Igawa, Naoki; Matsukawa, Takeshi*; Yoshida, Yukihiko*; Hoshikawa, Akinori*; Ishigaki, Toru*

no journal, , 

The magnetic behavior and magnetic structure of A$$_{2}$$Cu$$_{2}$$Mo$$_{3}$$O$$_{12}$$ (A=Rb, Cs) with CuO$$_{2}$$ ribbon chains have been studied by using specific heat measurement and neutron diffraction method. Cs$$_{2}$$Cu$$_{2}$$Mo$$_{3}$$O$$_{12}$$ showed collinear-antiferromagnetic structure analyzed by the neutron diffraction. The relation between magnetic behavior and magnetic for those materials are discussed.

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