Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 23

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Origin of the enhancement of electrocatalytic activity and durability of PtRu alloy prepared from a hetero binuclear Pt-Ru complex for methanol oxidation reactions

Okawa, Yukihisa*; Masuda, Takuya*; Uehara, Hiromitsu*; Matsumura, Daiju; Tamura, Kazuhisa; Nishihata, Yasuo; Uosaki, Kohei*

RSC Advances (Internet), 3(35), p.15094 - 15101, 2013/09

 Times Cited Count:9 Percentile:35.35(Chemistry, Multidisciplinary)

JAEA Reports

JRR-2 decommissioning activity, 2

Suzuki, Takeshi; Nakano, Masahiro; Okawa, Hiroshi; Terunuma, Akihiro; Kishimoto, Katsumi; Yano, Masaaki

JAERI-Tech 2005-018, 84 Pages, 2005/03

JAERI-Tech-2005-018.pdf:27.52MB

no abstracts in English

Journal Articles

Present status of JRR-2 decommissioning

Nakano, Masahiro; Okawa, Hiroshi; Suzuki, Takeshi; Kishimoto, Katsumi; Terunuma, Akihiro; Yano, Masaaki

Dekomisshoningu Giho, (30), p.11 - 24, 2004/09

Japan Research Reactor No.2(JRR-2), heavy water moderated and cooled tank type research reactor with maximum thermal power of 10MW,was operated for over 36 years, and was permanently shut down in December, 1996. In 1997, decommissioning plan was submitted to the STA, and dismantling was begun. Decommissioning program of JRR-2 is divided into 4 phases. Phase 1, 2 had already been completely finished without any trouble. Furthermore, the phase 3 was also finished in February, 2004 as planned. On exposure of worker in phase 1, 2 and 3, it was achieved to control lower than the estimate. On exposure of worker in phase 1, 2 and 3, it was achieved to control lower than the estimate. Reactor will be removed in phase 4 by one piece removal technique. The reactor building is planned to use effectively as a hot experimental facilities after decommissioning. The decommissioning plan was changed that the reactor would be kept in safety storage.

JAEA Reports

Design Study on In-core Breeding Concept Using Annular Thick Fuel Pins

Maeda, Seiichiro; Takashita, Hirofumi; Okawa, Tsuyoshi; Higuchi, Masashi*; Abe, Tomoyuki

JNC TN8400 2003-019, 185 Pages, 2003/08

JNC-TN8400-2003-019.pdf:11.78MB

We are studying on an in-core breeding concept as a candidate for a practical FBR fuel cycle system attainable in an early stage on the premise that sodium coolant and mixed oxide fuel should be adopted, since the technical issues with these combination are most advanced and common with the fuel cycle for a LWR-MOX system. An enhancement of fuel volume fraction using thick fuel pins enables the in-core breeding. The fuel material flow can be greatly lessened by minimizing amount of the blanket with the in-core breeding core. The low material flow leads to significant reduction of the fuel cycle cost. We investigated a 3500 MWth large-scale core adjusting several conditions presented in JNC's feasibility study program for a commercialized FBR system in this study. These were shown in this study that a discharged burnup averaged over the core and the blanket could reach approximately 130 GWd/t (core averaged about 150 GWd/t) within the maximum fast neutron fluence about 5$$times$$10$$^{23}$$/cm$$^{2}$$, that the small reactivity loss with burnup easily enabled long operation and that stable power distribution during operation significantly improved hydraulic property in this type core. We investigated measures to reduce sodium void reactivity, because core height enlargement to enhance neutron efficiency caused the increase of sodium void reactivity.We also investigated feasibility of a high breeding type core with low burnup considering a variety of FBR introducing scenarios and a trade-off correlation between breeding performance and burnup extension. The performance in this core design at core disruption accidents is not revealed enough. Further investigation should be made in detail to confirm that the in-core breeding concept could be accepted in a safety aspect.

JAEA Reports

JRR-2 decommissioning activity, 1

Nakano, Masahiro; Arigane, Kenji; Okawa, Hiroshi; Suzuki, Takeshi; Kishimoto, Katsumi; Terunuma, Akihiro; Yano, Masaaki; Sakuraba, Naotoshi; Oba, Nagamitsu

JAERI-Tech 2003-072, 92 Pages, 2003/08

JAERI-Tech-2003-072.pdf:6.99MB

The decommissioning plan of the Japan Research reactor No2(JRR-2), decommissioning activities until the first half of phase-3, radioactive wastes and exposure dose of workers are described in this report. Since the first criticality in October 1960, JRR-2 had been operated about 36 years for various experiments. However, JRR-2 was permanent shutdown in December 1996 based on JAERI's long term plan, and the decommissioning of the JRR-2 was started in August 1997. Decommissioning of the JRR-2 was planed for 11 years from 1997 to 2007 and the program was divided into 4 phases. The decommissioning activities of the phase-1, phase-2 and the first half of phase-3 had already completed as planned in March 1998, February 2000, March 2002, respectively. The decommissioning activities of the later half of Phase-3 (dismantling of the reactor cooling systems) are carrying out at present time with planed 2002 and 2003 fiscal years.

JAEA Reports

Irradiation tests of critical components for remote handling system in gamma radiation environment

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Furuya, Kazuyuki; *; Tada, Eisuke; Shibanuma, Kiyoshi; Koizumi, Koichi; Okawa, Yoshinao; Morita, Yosuke; et al.

JAERI-Tech 96-011, 111 Pages, 1996/03

JAERI-Tech-96-011.pdf:5.9MB

no abstracts in English

Journal Articles

R&D of 3-D base isolation system, part 3; The Experimental study on mechanical properties

Akutsu, Yoichi; Okawa, Yoshinao; Suzuki, Hideyuki; *; *; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.1147 - 1148, 1996/00

no abstracts in English

Journal Articles

R&D of seismic isolation system; R&D for fusion

Okawa, Yoshinao; Akutsu, Yoichi; Suzuki, Hideyuki; *; *; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.1047 - 1048, 1995/00

no abstracts in English

JAEA Reports

Irradiation tests of critical components for remote handling in gamma radiation environment

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi; Furuya, Kazuyuki; *; Tada, Eisuke; Shibanuma, Kiyoshi; Okawa, Yoshinao; Morita, Yosuke; Yokoo, Noriko*; et al.

JAERI-Tech 94-003, 73 Pages, 1994/08

[This article is unavailable to download the full text due to various reasons.]

Journal Articles

R&D of electrical monitoring technique for laminated rubber bearing, Part 1; Electrical characteristics of laminated rubber bearing

Akutsu, Yoichi; Okawa, Yoshinao; Suzuki, Hideyuki; *; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.1727 - 1728, 1994/00

no abstracts in English

Journal Articles

R&D of 3D seismic isolation system; R&D for fusion

Okawa, Yoshinao; Akutsu, Yoichi; Suzuki, Hideyuki; *; *; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.1725 - 1726, 1994/00

no abstracts in English

JAEA Reports

Design study of fusion experimental reactor tritium plant, II; Tritiated water and radioactive solid waste processing facilities

Yoshida, Hiroshi; ; Okawa, Yoshinao; Asahara, Masaharu*; Yokogawa, Nobuhisa*; Tanemori, Nozomu*; Horikiri, Hitoshi*

JAERI-M 93-136, 117 Pages, 1993/07

JAERI-M-93-136.pdf:3.01MB

no abstracts in English

JAEA Reports

Design study of fusion experimental reactor tritium plant, I; Tritium safety systems for reactor building

Yoshida, Hiroshi; ; Okawa, Yoshinao; Tanemori, Nozomu*; Horikiri, Hitoshi*

JAERI-M 93-107, 112 Pages, 1993/05

JAERI-M-93-107.pdf:3.29MB

no abstracts in English

Journal Articles

A Nuclide-separation wire precipitator for measurement of noble-gas fission products

Katagiri, Masaki; Kishimoto, Maki; Ito, Hirokuni; ; Fukushima, Masao; Okawa, Hiroshi;

Nuclear Instruments and Methods in Physics Research A, 327, p.463 - 468, 1993/00

 Times Cited Count:3 Percentile:43.05(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Real-time high-sensitivity fuel failure detection for HTGR

Katagiri, Masaki; Kishimoto, Maki; Ito, Hirokuni; Fukushima, Masao; Okawa, Hiroshi; ; ; Tobita, Tsutomu

Journal of Nuclear Science and Technology, 29(10), p.957 - 965, 1992/10

no abstracts in English

JAEA Reports

Japanese contributions to containment structure, assembly and maintenance and reactor building for ITER

Shibanuma, Kiyoshi; *; *; *; Okawa, Yoshinao; *; Tada, Eisuke; Koizumi, Koichi; *; Nishio, Satoshi; et al.

JAERI-M 91-080, 357 Pages, 1991/06

JAERI-M-91-080.pdf:12.46MB

no abstracts in English

JAEA Reports

Parameter study on Japanese proposal of ITER hydrogen isotope separation system

Yoshida, Hiroshi; Enoeda, Mikio; *; Tanaka, Shigeru; Okawa, Yoshinao; Nagakura, Masaaki*; *; *

JAERI-M 90-233, 38 Pages, 1991/01

JAERI-M-90-233.pdf:0.72MB

no abstracts in English

Journal Articles

Performance of fuel failure detection system for coated particle fuels

; ; ; ;

IEEE Transactions on Nuclear Science, NS-32, p.1209 - 1213, 1985/00

no abstracts in English

JAEA Reports

Oral presentation

Experimental Fast Reactor Joyo emergency operation act in Northeastern Japan earthquake 3.11

Karube, Koji; Aita, Tsuyoshi; Okawa, Toshikatsu

no journal, , 

no abstracts in English

23 (Records 1-20 displayed on this page)