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Journal Articles

Summary results of subsidy program for the "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris (Development of Technologies for Enhanced Analysis Accuracy and Thermal Behavior Estimation of Fuel Debris))"

Koyama, Shinichi; Nakagiri, Toshio; Osaka, Masahiko; Yoshida, Hiroyuki; Kurata, Masaki; Ikeuchi, Hirotomo; Maeda, Koji; Sasaki, Shinji; Onishi, Takashi; Takano, Masahide; et al.

Hairo, Osensui Taisaku jigyo jimukyoku Homu Peji (Internet), 144 Pages, 2021/08

JAEA performed the subsidy program for the "Project of Decommissioning and Contaminated Water Management (Development of Analysis and Estimation Technology for Characterization of Fuel Debris (Development of Technologies for Enhanced Analysis Accuracy and Thermal Behavior Estimation of Fuel Debris))" in 2020JFY. This presentation summarized briefly the results of the project, which will be available shortly on the website of Management Office for the Project of Decommissioning and Contaminated Water Management.

Journal Articles

Communication-overlap techniques for improved strong scaling of gyrokinetic Eulerian code beyond 100k cores on the K-computer

Idomura, Yasuhiro; Nakata, Motoki; Yamada, Susumu; Machida, Masahiko; Imamura, Toshiyuki*; Watanabe, Tomohiko*; Nunami, Masanori*; Inoue, Hikaru*; Tsutsumi, Shigenobu*; Miyoshi, Ikuo*; et al.

International Journal of High Performance Computing Applications, 28(1), p.73 - 86, 2014/02

 Times Cited Count:17 Percentile:78.64(Computer Science, Hardware & Architecture)

Journal Articles

Development of numerical techniques toward extreme scale fusion plasma turbulence simulations

Idomura, Yasuhiro; Nakata, Motoki; Yamada, Susumu; Machida, Masahiko; Imamura, Toshiyuki*; Watanabe, Tomohiko*; Nunami, Masanori*; Inoue, Hikaru*; Tsutsumi, Shigenobu*; Miyoshi, Ikuo*; et al.

Proceedings of 31st JSST Annual Conference; International Conference on Simulation Technology (JSST 2012) (USB Flash Drive), p.234 - 242, 2012/09

Journal Articles

Support system for training and education of future expert at PIE Hot Laboratories in Oarai JAEA; FEETS

Osaka, Masahiko; Donomae, Takako; Ichikawa, Shoichi; Sasaki, Shinji; Ishimi, Akihiro; Inoue, Toshihiko; Sekio, Yoshihiro; Miwa, Shuhei; Onishi, Takashi; Asaka, Takeo; et al.

Proceedings of 1st Asian Nuclear Fuel Conference (ANFC), 2 Pages, 2012/03

Support system for training and education of future expert in hot laboratories of Oarai-JAEA, named FEETS, is presented. The system has been established based on research results on both characterization of Oarai hot laboratory and user-needs. Various programs under FEETS are also introduced.

Journal Articles

Coulomb excitation of $$^{156}$$Gd

Sugawara, Masahiko*; Kusakari, Hideshige*; Yoshizawa, Hirokazu*; Inoue, Hikaru*; Morikawa, Tsuneyasu*; Shizuma, Toshiyuki; Srebrny, J.*

Physical Review C, 83(6), p.064308_1 - 064308_13, 2011/06

 Times Cited Count:6 Percentile:43.66(Physics, Nuclear)

Multiple Coulomb-excitation experiments for $$^{156}$$Gd were made with a 118 MeV $$^{32}$$S beam and a 225 MeV $$^{58}$$Ni beam. The ground-state band, the $$beta$$ band ($$K$$=0$$^{+}$$), and the $$gamma$$ band ($$K$$=2$$^{+}$$) were observed up to the 18$$^+$$, 14$$^+$$, and 12$$^+$$ states, respectively, while the octupole band ($$K$$=1$$^{-}$$) was observed up to the 15$$^-$$ state, through the analysis of particle-$$gamma$$-$$gamma$$ data. The intrinsic matrix elements entering the generalized intensity relations were obtained so as to reproduce the spin dependence of the $$E$$2 matrix elements extracted from the experimental results of particle-$$gamma$$ angular correlation for the transitions within each band and between each band and the ground-state band by the least-squares search code gosia. The change of characters in the $$beta$$ and $$gamma$$ bands is discussed as a possible cause for the variation of the $$E$$2 matrix elements in the higher-spin region.

JAEA Reports

Conceptual design and related R&D on ITER mechanical based primary pumping system

Tanzawa, Sadamitsu; Hiroki, Seiji; Abe, Tetsuya; Shimizu, Katsusuke*; Inoue, Masahiko*; Watanabe, Mitsunori*; Iguchi, Masashi*; Sugimoto, Tomoko*; Inohara, Takashi*; Nakamura, Junichi*

JAEA-Technology 2008-076, 99 Pages, 2008/12

JAEA-Technology-2008-076.pdf:35.19MB

The primary vacuum pumping system of the International Thermonuclear Experimental Reactor (ITER) exhausts a helium (He) ash resulting from the DT-burn with excess DT fueling gas, as well as performing a variety of functions such as pump-down, leak testing and wall conditioning. A mechanical based vacuum pumping system has some merits of a continuous pumping, a much lower tritium inventory, a lower operational cost and easy maintenance, comparing with a cryopump system, although demerits of an indispensable magnetic shield and insufficient performance for hydrogen (H$$_{2}$$) pumping are well recognized. To overcome the demerits, we newly fabricated and tested a helical grooved pump (HGP) unit suitable for H$$_{2}$$ pumping at the ITER divertor pressure of 0.1-10 Pa. Through this R&D, we successfully established many design and manufacturing databases of large HGP units for the lightweight gas pumping. Based on the databases, we conceptually designed the ITER vacuum pumping system mainly comprising the HGP with an optimal pump unit layout and a magnetic shield. We also designed conceptually the reduced cost (RC)-ITER pumping system, where a compound molecular pump combining turbine bladed rotors and helical grooved ones was mainly used. The ITER mechanical based primary pumping system proposed has eventually been a back-up solution, whereas a cryopump based one was formally selected to the ITER for construction.

Journal Articles

Research and development of minor actinide-containing fuel and target in a future integrated closed cycle system

Osaka, Masahiko; Serizawa, Hiroyuki; Kato, Masato; Nakajima, Kunihisa; Tachi, Yoshiaki; Kitamura, Ryoichi; Miwa, Shuhei; Iwai, Takashi; Tanaka, Kenya; Inoue, Masaki; et al.

Journal of Nuclear Science and Technology, 44(3), p.309 - 316, 2007/03

 Times Cited Count:29 Percentile:87.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Si substrate suitable for radiation-resistant space solar cells

Matsuura, Hideharu*; Iwata, Hiroshi*; Kagamihara, So*; Ishihara, Ryohei*; Yoneda, Masahiko*; Imai, Hideaki*; Kikuta, Masanori*; Inoue, Yuki*; Hisamatsu, Tadashi*; Kawakita, Shiro*; et al.

Japanese Journal of Applied Physics, Part 1, 45(4A), p.2648 - 2655, 2006/04

 Times Cited Count:15 Percentile:50.4(Physics, Applied)

no abstracts in English

Journal Articles

Development of minor actinide containing fuel/target for the use in a future integrated system of fast reactor and accelerator driven system

Osaka, Masahiko; Serizawa, Hiroyuki*; Kato, Masato; Inoue, Masaki; Nakajima, Kunihisa*; Tachi, Yoshiaki; Kitamura, Ryoichi; Oki, Shigeo; Miwa, Shuhei; Iwai, Takashi*; et al.

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

Development of minor actinide containing fuel/target, i.e., (Pu,Am)O$$_{2}$$-MgO, (Pu,Np)O$$_{2}$$-MgO, (U,Pu,Np)O$$_{2}$$, (U,Pu,Np)N and (Pu,Np,Zr)N, for the use in a future integrated system of fast reactor and accelerator driven system is underway as a collaborative work between JAERI and JNC. The present statuses of fabrication test and property measurements are given. Irradiation test in the experimental fast reactor JOYO is also mentioned.

JAEA Reports

Selection Study of Am-Target Candidates for the Irradiation in Fast Reactors

Osaka, Masahiko; Yoshimochi, Hiroshi; Donomae, Takako; Inoue, Masaki

JNC TN9420 2003-002, 42 Pages, 2003/10

JNC-TN9420-2003-002.pdf:1.49MB

Selection study of Am target candidates for the irradiation in the experimental fast reactor JOYO was performed by the investigation of previously reported studies as a part of JNC-JAERI joint project. Criteria of the selection of inert matrix for the Am target was decided and preliminary selection was carried out on the basis of the investigation results of the present status of development of target and several selection studies in the world. Detailed investigation of the properties such as thermal conductivity, irradiation behavior,fabrication technique on seven pre-selected candidates, specifically ZrO2, Al2O3, MgO, SiC, Si3N4, MgAl2O4 and TiN, was then performed. Five matrices for Am target candidates, ZrO2, MgO, SiC, Si3N4 and TiN,were consequently selected on considering the criteria,in particular, adaptability of the fabrication process were also designed and decided as follows: Dispersed type of Am oxide particle (dia:100/300 micro meter)into MgO (1) Am oxideparticle fabrication by dry route ; i.e. compacting of Am oxide powder, crushing and sieving (2) Mixing of Am oxide particle with MgO particle made by spray dry (3) Pelletizing by uni-axial press and sintering in one atm of inert atmosphere Mixed type of Am oxide (1) Mixing of Am oxide powder with material (SiC, Si3N4 or TiN) powder (2) Pelletizing by uni-axial press and sintering in one atm of inert atmosphere Fabrication test and property measurement will be conducted for the final decision of Am-containing target.

Journal Articles

An Economic index regarding market creation of products obtained from utilization of radiation and nuclear energy, 4; Comparison between Japan and U. S. A.

Yanagisawa, Kazuaki; Kume, Tamikazu; Makuuchi, Keizo; Tagawa, Seiichi*; Chino, Mitsuo*; Inoue, Tomio*; Takehisa, Masaaki*; Hagiwara, Miyuki*; Shimizu, Masahiko*

Journal of Nuclear Science and Technology, 39(10), p.1120 - 1124, 2002/10

 Times Cited Count:3 Percentile:24.12(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Power-to-melts of uranium-plutonium oxide fuel pins at a beginning-of-life condition in the experimental fast reactor JOYO

Inoue, Masaki; ; ; ; Sekine, Takashi; Osaka, Masahiko

Journal of Nuclear Materials, 323(1), p.108 - 122, 2002/00

 Times Cited Count:8 Percentile:50.89(Materials Science, Multidisciplinary)

None

JAEA Reports

Design and installation of W-shaped divertor in JT-60U

; Masaki, Kei; ; Morimoto, Masaaki*; *; Sakurai, Shinji; *; Saido, Masahiro; Inoue, Masahiko*; *; et al.

JAERI-Tech 98-049, 151 Pages, 1998/11

JAERI-Tech-98-049.pdf:6.45MB

no abstracts in English

Journal Articles

Development of a compact W-shaped pumped divertor in JT-60U

Sakurai, Shinji; Hosogane, Nobuyuki; Masaki, Kei; ; ; *; *; Shimizu, Katsuhiro; Akino, Noboru; Miyo, Yasuhiko; et al.

Fusion Engineering and Design, 39-40, p.371 - 376, 1998/00

 Times Cited Count:5 Percentile:44.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of electrolytic reactor for processing of gaseous tritiated compounds

Konishi, Satoshi; Maruyama, T.*; *; Inoue, Masahiko*; *

Fusion Engineering and Design, 39-40, p.1033 - 1039, 1998/00

 Times Cited Count:7 Percentile:54.51(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Design and evaluation of super-heat-resisting Nb-based and Mo-based alloys

Morinaga, Masahiko*; *; *; *; Inoue, Satoshi*

PNC TJ9603 96-001, 79 Pages, 1996/03

PNC-TJ9603-96-001.pdf:3.48MB

[PURPOSE] In order to develop the frontier domain of technique for the high temperature liquid alkali metal, candidate Nb-based and Mo-based alloys are needed. They are needed to have excellent compatibility with liquid Li (max. 1200$$^{circ}$$C) and super-heat-resistance. In this study, alloy design using a d-electrons alloy theory and estimation of designed alloy were performed. [EXPERIMENTAL METHODS] (1)Workability : A bend test was carried out with the provisionally designed Mo-based alloys, but by modifying the compositions by adding intergranular strengthening elements, Ti, B, C, Hf, into them to improve the ductility. (2)Corrosion resistance to liquid Li : The provisionally desingned Nb-based alloys were immersed in liquid Li at 1200$$^{circ}$$C for three hundred hours, and the weight change due to the corrosion was measured. The corrosion surface was also analyzed using SEM and EPMA. In addition, a similar corrosion test was carried out with binary Nb-based and Mo-based alloys. (3)Embrittlement at 800$$^{circ}$$C : A series of experiments such as the hardness test, X-ray analysis and microstructure observation was perfomed with the Nb-1Zr alloy which was creep-tested at 800$$^{circ}$$C or 1200$$^{circ}$$C. Also, a Nb-1Zr alloy specimen which was not creep-tested, was used as a reference specimen. [RESULTS AND DISCUSSIONS] (1)Workability : The Ti addition into the Mo-based alloys was effective in improving workability. The brittleness of Mo may be caused by the existence of oxygen in the grain boundaries, so that the formation of Ti oxides probably weakened the oxygen effect, resulting in the better workability of the alloy. However, B, C and Hf additions into Mo-based alloys never improved the workability. (2)Corrosion resistance to liquid Li : Many cracks were observed on the corroded surface of the provisionally designed Nb-based alloys despite the addition of a corrosion resistant element, Hf, into them. In paticular, such cracks were developed ...

Journal Articles

None

Saito, Junichi; Tachi, Yoshiaki; Kano, Shigeki; Morinaga, Masahiko*; *; Inoue, Satoshi*

PP57$$sim$$66, (97), p.57 - 66, 1996/03

None

Journal Articles

Electrical insulation and conduction coating for fusion experimental devices

Onozuka, Masanori*; Tsujimura, Seiji*; Toyoda, Masahiko*; Inoue, Masahiko*; Abe, Tetsuya; Murakami, Yoshio

Fusion Technology, 29(1), p.73 - 82, 1996/01

 Times Cited Count:9 Percentile:62.96(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design of a compact W-shaped pumped divertor in JT-60U

Sakurai, Shinji; Hosogane, Nobuyuki; ; Masaki, Kei; ; *; *; Takahashi, Shoryu*; Saido, Masahiro; Inoue, Masahiko*; et al.

Fusion Technology 1996, 0, 4 Pages, 1996/00

no abstracts in English

JAEA Reports

None

Morinaga, Masahiko*; Saito, Junichi*; Murata, Yoshinori*; Kano, Shigeki; *; Tachi, Yoshiaki; Inoue, Satoshi*

PNC TY9623 95-001, 165 Pages, 1995/03

PNC-TY9623-95-001.pdf:5.61MB

None

42 (Records 1-20 displayed on this page)