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Journal Articles

Study of the calculation method for the elastic follow-up coefficient by inelastic analysis

Watanabe, Sota*; Kubo, Koji*; Okajima, Satoshi; Wakai, Takashi

Nippon Kikai Gakkai M&M 2017 Zairyo Rikigaku Kanfarensu Koen Rombunshu (Internet), p.581 - 585, 2017/10

no abstracts in English

Journal Articles

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.

Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12

 Times Cited Count:91 Percentile:5.41(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Cold moderator design of JSNS 1 MW pulse source

Kogawa, Hiroyuki; Ishikura, Shuichi*; Hino, Ryutaro; Kato, Takashi; Aso, Tomokazu; Sato, Hiroshi; Harada, Masahide; Kai, Tetsuya; Teshigawara, Makoto; Maekawa, Fujio; et al.

Proceedings of ICANS-XVI, Volume 2, p.635 - 644, 2003/07

no abstracts in English

JAEA Reports

Structual design study of a proton beam window for a 1-MW spallation neutron source

Teraoku, Takuji*; Terada, Atsuhiko*; Maekawa, Fujio; Meigo, Shinichiro; Kaminaga, Masanori; Ishikura, Shuichi*; Hino, Ryutaro

JAERI-Tech 2003-026, 77 Pages, 2003/03

JAERI-Tech-2003-026.pdf:19.78MB

A 1-MW spallation neutron source aiming at materials and life science researches will be constructed under the JAERI-KEK Proton Accelerator Project(J-PARC). The proton beam window functions as a boundary wall between a high vacuum area and a helium atmosphere and it is cooled by light water because high heat-density is generated in the window material by interactions with the proton beam. Then, uniformity of the water flow is requested at the window to suppress a hot-spot that causes excessive thermal stress and cooling water boiling. Also, the window has to be strong enough in its structure for inner stress due to water pressure and thermal stress due to heat generation. In this report, we propose two types of proton beam windows, flat-type and curved-type. We evaluated the strength of structure and thermal hydraulic analysis. As a result, it was found that sufficient heat removal was assured with uniform water flow at the window, and the stress could be maintained below allowable stress values. Accordingly, it was confirmed that the proton beam window designs were feasible.

Journal Articles

Safety activities in JAERI related to ITER

Ohira, Shigeru; Tada, Eisuke; Hada, Kazuhiko; Neyatani, Yuzuru; Maruo, Takeshi; Hashimoto, Masayoshi*; Araki, Takao*; Nomoto, Kazuhiro*; Tsuru, Daigo; Ishida, Toshikatsu*; et al.

Fusion Engineering and Design, 54(3-4), p.515 - 522, 2001/04

 Times Cited Count:3 Percentile:70.15

no abstracts in English

JAEA Reports

None

Federation of Electric Power Companies of Japan*

JNC-TY1400 2000-001, 464 Pages, 2000/03

JNC-TY1400-2000-001.pdf:16.87MB

None

JAEA Reports

Design concepts for overpack

*; *; Tanai, Kenji

JNC-TN8400 99-047, 54 Pages, 1999/11

JNC-TN8400-99-047.pdf:3.16MB

This paper reports on the design process for a carbon-steel overpack as a key component in the engineered barrier system of a deep geological repository described in the 2nd progress report. The results of the research and development regarding design requirements, configuration, manufacturing and inspection of overpack are also described. The concept of a composite overpack composed of two different materials is also considered. First, the design requirements for an overpack and presume environmental and design conditions for a repository are provided. For a candidate material of carbon steel overpack, forging material is selected considering enough experience of using this material in nuclear power boilers and other components. Second, loading conditions after emplacement in a repository are set and the pressure-resistant thickness of overpack is calculated. The corrosion thickness to achieve an assigned 1000 year life time and the required thickness to prevent radiolysis of ground water which might enhance corrosion rate are also determined. As aresult, the total required thickness of a carbon-steel overpack is conservatively estimated to 190 mm. This is a reduction of about 30% from the previous estimate provided in the 1st Progress Report. Additional items that must be considered in manufacturring and operating overpacks (i.e. sealing of vitrified waste, examination of main body and sealing welding, mechanism of handling) are evaluated on the basis of current technology, specific future data needs are identified. With respect to the concept of composite overpack (i.e., an outer vessel to provide corrosion-allowance or corrosion-resistant performance and an inner vessel to provide pressure-resistance), the differences in design concepts between the carbon-steel overpack and such composite overpacks are analyzed. Future data needs and analytical capabilities with respect to overpacks are also summarized.

Journal Articles

Dedicated accelerator-driven system for nuclear waste transmutation

Takizuka, Takakazu; Tsujimoto, Kazufumi; Sasa, Toshinobu; Takano, Hideki

Proceedings of the 3rd International Conference on Accelerator Driven Transmutation Technologies and Applications (CD-ROM), 12 Pages, 1999/06

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:52.35

no abstracts in English

JAEA Reports

Structural integrity of heavy liquid-metal target instabled in neutron spallation facility, Part 1; Preliminary study on stress wave generated by irradiating pulsed-proton beam

Ishikura, Shuichi*; Kikuchi, Kenji; Futakawa, Masatoshi; Hino, Ryutaro

JAERI-Tech 97-037, 36 Pages, 1997/08

JAERI-Tech-97-037.pdf:0.92MB

no abstracts in English

Journal Articles

Fracture toughness tests of nuclear graphites

Ishiyama, Shintaro; Eto, Motokuni

23nd Biennial Conference on Carbon (CARBON '97) Extended Abstracts and Program, Vol,2, p.232 - 233, 1997/00

no abstracts in English

Journal Articles

Present activities preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor

Miya, Kenzo*; ; Takatsu, Hideyuki; Hada, Kazuhiko; Koizumi, Koichi; Jitsukawa, Shiro; ; Okawa, Yoshinao; Shimakawa, T.*; Aoto, Kazumi*; et al.

Fusion Engineering and Design, 31, p.145 - 165, 1996/00

 Times Cited Count:3 Percentile:65.05

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

; *; *; *; *

PNC-TJ9365 95-001, 110 Pages, 1995/12

PNC-TJ9365-95-001.pdf:7.16MB

None

Journal Articles

Structural design code

Miya, Kenzo*; ; Takatsu, Hideyuki

Kikai No Kenkyu, 47(1), p.179 - 184, 1995/00

no abstracts in English

Journal Articles

Creep properties with short period excessive loadings on a nickel-base heat-resistant alloy hastelloy XR

Tsuji, Hirokazu; *; *; Nakajima, Hajime

Journal of Nuclear Science and Technology, 31(4), p.274 - 278, 1994/04

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Structural design of pressure vessel of High Temperature Engineering Test Reactor

Kurihara, Ryoichi; Tachibana, Yukio; Nishihara, Tetsuo; Maruyama, So; Shiozawa, Shusaku; *

Atsuryoku Gijutsu, 32(3), p.154 - 165, 1994/00

no abstracts in English

JAEA Reports

Creep properties with short period excessive loadings on a nickel-base heat-resistant alloy Hastelloy XR

Tsuji, Hirokazu; *; *; Nakajima, Hajime

JAERI-M 93-144, 69 Pages, 1993/07

JAERI-M-93-144.pdf:1.74MB

no abstracts in English

JAEA Reports

Investigation on thermohydraulics optimization in the lower plenum of large scale FBR

;

PNC-TN9410 93-092, 93 Pages, 1993/04

PNC-TN9410-93-092.pdf:4.85MB

In-vessel thermohydraulic analysis using a multi-dimensional code AQUA was conducted to investigate thermohydralic conditions in the lower plenum of a large scale liquid metal fast breeder reactor (LMFBR). In the investigation, it was focused in a effective mixing volume in the plenum and in a loose parts trapping by hydraulic forces. Through the analysis by the AQUA code and discussions based on their results, the following results have been obtained: [In-Flow Allotment Characteristics at the Truss] (1)Mass flow rate between lower flow holes and side flow holes to the truss was balanced in the case of 22.5$$^{circ}$$ for the coolant inlet angle to the plenum under a full flow condition. (2)The above result did not change with the transient conditions simulating a manual reactor trip event. [Effective Mixing volume] (1)From the transient calculation, it was clear that the effective mixing volume was corresponded to 77-79% of the total volume in the plenum. [Loose Parts Trapping] (1)A condition (W$$<$$1.0m/s) to trap loose parts by hydraulic forces was not satisfied under parametric calculations only considered here.

38 (Records 1-20 displayed on this page)