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Journal Articles

First flight demonstration of glass-type space solar sheet

Shimazaki, Kazunori*; Kobayashi, Yuki*; Takahashi, Masato*; Imaizumi, Mitsuru*; Murashima, Mio*; Takahashi, Yu*; Toyota, Hiroyuki*; Kukita, Akio*; Oshima, Takeshi; Sato, Shinichiro; et al.

Proceedings of 40th IEEE Photovoltaic Specialists Conference (PVSC-40) (CD-ROM), p.2149 - 2154, 2014/06

The electrical performance of a glass-type space solar sheet (G-SSS) was demonstrated in space. G-SSS comprises InGaP/GaAs dual-junction and InGaP/GaAs/InGaAs triplejunction solar cells. It is lightweight solar generation sheet, less than 0.5 mm thick. It is mounted on the "HISAKI" (SPRINT-A) small scientific satellite, which was launched on September 14, 2013. The initial flight data were successfully acquired and this flight demonstration was a world-first experiment for G-SSS using III-V multi-junction thin-film solar cells. The cells demonstrated superior performance and the electrical outputs matched the flight prediction.

Journal Articles

Post-irradiation examination on particle dispersed rock-like oxide fuel

Shirasu, Noriko; Kuramoto, Kenichi*; Yamashita, Toshiyuki; Ichise, Kenichi; Ono, Katsuto; Nihei, Yasuo

Journal of Nuclear Materials, 352(1-3), p.365 - 371, 2006/06

 Times Cited Count:4 Percentile:66.24(Materials Science, Multidisciplinary)

To evaluate irradiation behavior of the ROX fuel, irradiation experiment was carried out using 20% enriched U instead of Pu. Three fuels were prepared; a single phase fuel of YSZ containing UO$$_{2}$$ (U-YSZ), two particle-dispersed fuels of U-YSZ particle in spinel or corundum matrix. The U-YSZ particles were prepared by crashing presintered U-YSZ pellets and by sieving them. These fuels were irradiated in Japan Research Reactor No.3 for 13 cycles, about 300 days. Though many cracks were observed in the pellets by X-ray photographs, significant appearance changes were not observed for all fuel pins. Distribution of typical FPs was analyzed by the $$gamma$$ scanning over the fuel pin. Non-volatile nuclide remained in the fuel pellet. On the other hand, a part of Cs moved to the gaps between the pellets and to the insulators. $$^{134}$$Cs and $$^{137}$$Cs showed different distributions at the plenum. Fuel pellets were taken out from fuel pins without bonding. Spinel decomposition and subsequent restructuring were not observed probably due to low irradiation temperature.

Journal Articles

The Effect of neutron irradiation on mechanical properties of YAG laser weldments using previously irradiated material

Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Kalinin, G.*; Nagao, Yoshiharu; Takada, Fumiki; Nishikawa, Masahiro*

Journal of Nuclear Materials, 340(1), p.57 - 63, 2005/04

 Times Cited Count:3 Percentile:73.42(Materials Science, Multidisciplinary)

This study was performed to clear the effect of neutron re-irradiation on mechanical properties to welding material un-irradiated and irradiated stainless steel. The effect of re-irradiation to these weldaments were evaluated by tensile tests, metallographical observation and hardness test. The result of tensile tests shows that ultimate tensile strength of all joints specimen were almost similar, 0.2% yield strength and total elongation were depend on the irradiation damage and weldaments or not. Therefore, fracture mechanism was not change by re-irradiation. However, brittlement of material was depend on irradiation damage and the property of deformation was sensitive by the effect of irradiation damage or the effect of welding heat.

JAEA Reports

Examination on detaching method of an irradiated mock-up with Li$$_{2}$$TiO$$_{3}$$ pebble bed from the core of JMTR

Ikeshima, Yoshiaki; Ishida, Takuya*; Tsuchiya, Kunihiko; Tomita, Kenji; Ebisawa, Hiroyuki; Magome, Hirokatsu; Nakamichi, Masaru*; Kitajima, Toshio; Kawamura, Hiroshi

JAERI-Tech 2005-005, 37 Pages, 2005/02


no abstracts in English

JAEA Reports

A Preliminary irradiation test of the new ceramics materials for the innovative basic research on high-temperature engineering

Baba, Shinichi; Yamaji, Masatoshi*; Shibata, Taiju; Ishihara, Masahiro; Sawa, Kazuhiro

JAERI-Tech 2005-002, 83 Pages, 2005/02


The innovative basic research concerns the association of basic and technology with high temperature irradiation environments. The direction of research involves novel and bold challenges both in nuclear and non-nuclear fields. The innovative basic research on high-temperature engineering is one of the key subjects using the HTTR as well as other research reactors. The aim of this paper is to describe the preliminary irradiated test conditions such as irradiated fluence, irradiated temperature and installed specimen on the capsules, and also to show the specifications and performances of the apparatus for Post/Ante Irradoation Experiment.

Journal Articles

$$gamma$$-ray irradiation experiments of collimator key components for the 3GeV-RCS of J-PARC

Kinsho, Michikazu; Ogiwara, Norio; Masukawa, Fumihiro; Takeda, Osamu; Yamamoto, Kazami; Kusano, Joichi

Proceedings of 2005 Particle Accelerator Conference (PAC '05) (CD-ROM), p.1309 - 1311, 2005/00

It was success to develop the radiation resistant components using for beam collimator. Turbo molecular pump could be operated more than 15 MGy of $$gamma$$ ray irradiation dose. Stepping motor developed at JAERI could be operated with good performance in the $$gamma$$ ray dose of more than 70 MGy. PEEK sheathed cables and connector have kept good performance during $$gamma$$ ray irradiation more than the dose of 10 MGy. It was cleared that the function of the heat pipe disappeared at 30 kGy $$gamma$$ ray irradiation dose.

Journal Articles

Development of Rock-like Oxide Fuel, an innovative nuclear fuel for burning plutonium

Yamashita, Toshiyuki

Seramikkusu, 39(10), p.817 - 821, 2004/10

no abstracts in English

Journal Articles

Gamma-ray irradiation experiment of turbo molecular pump

Kinsho, Michikazu; Ogiwara, Norio; Wada, Kaoru*; Yoshida, Motoo*; Nakayasu, Tatsuo*; Yamato, Yukio*

Vacuum, 73(2), p.175 - 180, 2004/03

 Times Cited Count:2 Percentile:87.23(Materials Science, Multidisciplinary)

The turbo molecular pump which can be operated exposed to high radiation has been developing at JAERI and Osaka Vacuum Ltd., because it is planed to use this turbo molecular pump for the 3GeV-RCS of the J-PARC project. The goal of irradiation dose is 30 MGy because the cumulative energy dose due to radiation is approximately estimated to be on the order of 100 MGy for 30 years of the 3GeV-RCS operation. In order to know radiation damage of turbo molecular pump, gamma-ray irradiation experiment has been performed at JAERI. The turbo molecular pump could operate properly less than 3.5 MGy absorption dose under gamma-ray irradiation environment. Since the elongation of elastomer vacuum seals became small due to exposed to radiation, this radiation damage of elastomer seals causes leak. The turbo molecular pump components except the elasomer seals, for example motor coil, control sensor, and etc, have kept high performance more than 7 MGy absorption dose. The turbo molecular pump without elastomer seals has been developed and the irradiation test will be started form April.

JAEA Reports

The Present situation and future utilization of testing reactors in the world

Ito, Haruhiko; Ide, Hiroshi; Yamaura, Takayuki; Tsuji, Tomoyuki

JAERI-Review 2004-001, 39 Pages, 2004/02


no abstracts in English

Journal Articles

Evaluation of effective thermal diffusivity of Li$$_2$$TiO$$_3$$ pebble bed under neutron irradiation

Kawamura, Hiroshi; Kikukawa, Akihiro*; Tsuchiya, Kunihiko; Yamada, Hirokazu*; Nakamichi, Masaru; Ishitsuka, Etsuo; Enoeda, Mikio; Ito, Haruhiko

Fusion Engineering and Design, 69(1-4), p.263 - 267, 2003/09

 Times Cited Count:2 Percentile:79.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

In-situ irradiation test of mica substrate bolometer at the JMTR reactor for the ITER diagnostics

Nishitani, Takeo; Shikama, Tatsuo*; Reichle, R.*; Hodgson, E. R.*; Ishitsuka, Etsuo; Kasai, Satoshi; Yamamoto, Shin

Fusion Engineering and Design, 63-64, p.437 - 441, 2002/12

 Times Cited Count:13 Percentile:33.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of the I-I type irradiation equipment for the HTTR

Shibata, Taiju; Kikuchi, Takayuki; Miyamoto, Satoshi*; Ogura, Kazutomo*; Ishigaki, Yoshinobu*

FAPIG, (161), p.3 - 7, 2002/07

no abstracts in English

Journal Articles

Irradiation effects on diagnostic components for ITER

Nishitani, Takeo; Shikama, Tatsuo*; Reichle, R.*; Sugie, Tatsuo; Kakuta, Tsunemi; Kasai, Satoshi; Ishitsuka, Etsuo; Yamamoto, Shin

Purazuma, Kaku Yugo Gakkai-Shi, 78(5), p.462 - 467, 2002/05

no abstracts in English

JAEA Reports

Irradiation data analysis program on fusion blanket

Nakamichi, Masaru; Akutsu, Hisashi*; Yamaguchi, Katsuyoshi*; Tsuchiya, Kunihiko; Kawamura, Hiroshi; Ito, Haruhiko

JAERI-Data/Code 2002-010, 288 Pages, 2002/03


no abstracts in English

JAEA Reports

Data on HTTR irradiation test specimens; The First and second irradiation tests

Baba, Shinichi; Ishihara, Masahiro; Suzuki, Yoshio*; Takahashi, Tsuneo*; Hoshiya, Taiji

JAERI-Data/Code 2002-008, 126 Pages, 2002/03


no abstracts in English

JAEA Reports

Annual report of JMTR, No.15, FY2000; April 1, 2000 to March 31, 2001

Department of JMTR

JAERI-Review 2002-001, 86 Pages, 2002/02


During the FY2000 (April 2000 to March 2001), the JMTR (Japan Materials Testing Reactor) was operated in 6 operation cycles (130 days) for irradiation studies on the IASCC of the LWR materials, development of actinide contained uranium-hydride fuels, development of fusion blanket materials, and so on. The total number of capsules and hydraulic rabbits irradiated were 132 and 79, respectively.Technology development programs were conducted in the following fields. As concerning to the utilization of JMTR, a irradiation facility for the IASCC studies, irradiation capsules for RPV surveillance specimen and automatic temperature control system for irradiation capsules were developed.New efficient production process was developed for pebble type tritium breeder material for fusion reactor blanket, and tritium generation/recovery behavior under irradiation was investigated using pebble packed test piece.This report summarizes these activities performed in the department of JMTR during the FY2000.

JAEA Reports

Proceedings of the Seminar on the Utilization of Neutron Irradiation; March 9th 2000, Tokai

Department of JMTR, Oarai; Department of Research Reactor, Tokai; Department of Hot Laboratories, Tokai

JAERI-Conf 2001-018, 109 Pages, 2002/01


The “Seminar on the Utilization of Neutron Irradiation" was held on March 9th 2000 in Tokai establishment as a part of activities of the “Program Committee for Neutron Irradiation". The topics presented in the seminar included the recent irradiation studies on the materials for the light water reactors, development of fusion reactor materials and materials used under high temperature, application of neutron activation and recent activities in the post irradiation examinations. This report contains the shortpapers and the copies of the OHPs presented at the seminar.

JAEA Reports

Development of magnetic j$$times$$B sensor

Kasai, Satoshi; Nakayama, Takahide*; Ishitsuka, Etsuo

JAERI-Tech 2001-082, 23 Pages, 2001/12


The improved mechnical sensor, j$$times$$B has been desiged and developed. Materials of a load cell (strain gauge and sensor beam) and sensing coil/frame are selected to be neutron resistance. In order to reduce temperature drift of the sensor signal, four strain gauges with the same electrical property and geometrical size are bonded on the sensor beam by Al$$_{2}$$O$$_{3}$$ spraying process. These gauges form an electrical bridge circuit. The zero-level drift of the output of the load cell was reduced to about 1/20 compared with the old sensor. Non-linearity of the output of load cell and sensitivity of the j$$times$$B sensor was observed. The deviation of sensitivity from the fitting line was less than 7 % in high magnetic field region. The sensitivity of the sensor was gradually decreased by about 30 % at neutron fluence of (1.8$$sim$$2.8)$$times$$10$$^{23}$$ n/m$$^{2}$$ in high magnetic field region.

Journal Articles

In-situ tritium release behavior from Li$$_{2}$$TiO$$_{3}$$ pebble-bed

Tsuchiya, Kunihiko; Kikukawa, Akihiro*; Yamaki, Daiju; Nakamichi, Masaru; Enoeda, Mikio; Kawamura, Hiroshi

Fusion Engineering and Design, 58-59, p.679 - 682, 2001/11

 Times Cited Count:3 Percentile:71.32(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Present status and future plan of IASCC research program at JAERI

Tsuji, Hirokazu; Tsukada, Takashi; Kaji, Yoshiyuki; Ugachi, Hirokazu; Nakano, Junichi; Miwa, Yukio

JAERI-Conf 2001-008, p.187 - 203, 2001/07

no abstracts in English

135 (Records 1-20 displayed on this page)