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Journal Articles

A New method for the quantitative analysis of the scale and composition of nanosized oxide in 9Cr-ODS steel

Onuma, Masato*; Suzuki, Junichi; Otsuka, Satoshi; Kim, S.-W.; Kaito, Takeji; Inoue, Masaki; Kitazawa, Hideaki*

Acta Materialia, 57(18), p.5571 - 5581, 2009/10

 Times Cited Count:117 Percentile:97.23(Materials Science, Multidisciplinary)

Journal Articles

Clarification of strain limits considering the ratcheting fatigue strength of 316FR steel

Isobe, Nobuhiro*; Sukekawa, Masayuki*; Nakayama, Yasunari*; Date, Shingo*; Otani, Tomomi*; Takahashi, Yukio*; Kasahara, Naoto; Shibamoto, Hiroshi*; Nagashima, Hideaki*; Inoue, Kazuhiko*

Nuclear Engineering and Design, 238(2), p.347 - 352, 2008/02

 Times Cited Count:21 Percentile:78.82(Nuclear Science & Technology)

The effect of ratcheting on fatigue strength was investigated in order to rationalize the strain limit as a design criterion of commercialized fast reactor systems. Ratcheting fatigue tests were conducted at 550$$^{circ}$$C. Duration of the ratchet straining was set for a certain number of strain cycles taking the loading condition of fast reactors into account, and the number of cycles for strain accumulation was defined as the ratchet-expired cycle. Fatigue lives decrease as the accumulated strain by ratcheting increases. Fatigue life reduction was negligible when the maximum mean stress was less than 25 MPa, corresponding to an accumulated strain of 2.2 percent. Accumulated strain is limited to 2 percent in the present design guidelines and this strain limit is considered effective to avoid reducing fatigue life by ratcheting. Micro-crack growth behaviors were also investigated in these tests in order to discuss the life reduction mechanisms in ratcheting conditions.

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

Journal Articles

Application of Classification Method to obtain Primary Stresses without Evaluation Sections to Perforated Structures

Nagashima, Hedeaki; Shibamoto, Hiroshi; Inoue, Kazuhiko; kasahara, Naoto; Sadahiro, Daisuke*

Proceedings of 2005 ASME International Mechanical Engineering Congress and Exposition (CD-ROM), 0 Pages, 2005/08

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

Journal Articles

DEVELOPMENT OF GUIDELINE FOR THERMAL LOAD MODELING

Shibamoto, Hiroshi; Nagashima, Hedeaki; Inoue, Kazuhiko; Kasahara, Naoto; Jimbo, Masakazu*; Furuhashi, Ichiro*

Proceedings of 2005 ASME International Mechanical Engineering Congress and Exposition (CD-ROM), 0 Pages, 2005/08

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

Journal Articles

Recent developments for fast reactor structural design standard (FDS)

Kasahara, Naoto; Nakamura, Kyotada; Ito, Kei; Shibamoto, Hiroshi; Nagashima, Hideaki; Inoue, Kazuhiko

Transactions of 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT-18), p.1131 - 1140, 2005/08

We carried out reflection seismic and multi-offset VSP surveys at JNC Shobasama-site to develop the investigation technique in the granite area, and evaluated the applicability of these geophysical methods. As the result of this study, we consider that a) It is possible to infer the existence of the lower angle fracture zone in the granite by reflection seismic survey and b) Multi-offset VSP supplements the result of reflection seismic survey and it is possible to infer the distribution of the fracture zone in deeper area in the granite.

JAEA Reports

Study on advanced structual design for commercialized fast breeder reactors

Morishita, Masaki; Aoto, Kazumi; Kasahara, Naoto; Asayama, Tai; Nakamura, Kyotada*; Inoue, Kazuhiko*; Nagashima, Hideaki*

JNC TY9400 2005-012, 2351 Pages, 2005/07

JNC-TY9400-2005-012-1.pdf:135.59MB
JNC-TY9400-2005-012-2.pdf:63.18MB

Aiming to realize safety and economcal commercialized fast reactor, R6D activities on structural design methods launched FY 2000 and continued up to FY 2004. The reserch scope was identified as (1)FBR Structural Design Standard (FDS), (2)Standardiation of new material and (3)System Based Code for Integrity. Since this fisical year is the Last year for the R6D activities, the results are summarized as FBR Design Stndard (interim proposal), Standadization of new material (interim prpposal) etc. The results of this report include a part of

Journal Articles

Simulation of technetium behaviour in Purex extraction system

Fujine, Sachio; Tachimori, Shoichi; ; Suzuki, Shinichi; Maeda, Mitsuru; *; *

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management; RECOD '94, Vol.1, 0, 14 Pages, 1994/00

no abstracts in English

JAEA Reports

Journal Articles

Application of MINCS code to numerical benchmark problems for two-fluid model

Hirano, Masashi; Watanabe, Tadashi; Tanabe, Fumiya; *; *; Kamo, Hideki*;

Konsoryu, 1(1), p.79 - 95, 1987/00

no abstracts in English

Journal Articles

Evaluation of interfacial shear model for bubbly flow regime with the MINCS code

Hirano, Masashi; ; ; ; *; *; *;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 80, 1986/00

no abstracts in English

Journal Articles

Development of transient two-phase flow analyzer:MINCS

; Hirano, Masashi; ; ; *; *; *

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.1 - 72, 1986/00

no abstracts in English

Journal Articles

Double heterogeneity effect of fuel pin and subassembly in a fast power reactor

Nakagawa, Masayuki; *

Nuclear Science and Engineering, 53(2), p.214 - 228, 1983/00

no abstracts in English

Journal Articles

Doppler effect of structural materials in fast reactors

; *

Journal of Nuclear Science and Technology, 18(4), p.315 - 318, 1981/00

 Times Cited Count:0 Percentile:0.27(Nuclear Science & Technology)

no abstracts in English

Oral presentation

R&D issues in structural design standard of fast reactor, 16; Application of inelastic analysis to piping design

Fujimata, Kazuhiro*; Nagashima, Hideaki*; Sukekawa, Masayuki*; Shibamoto, Hiroshi; Inoue, Kazuhiko*; Kasahara, Naoto

no journal, , 

no abstracts in English

Oral presentation

Study on environmental radiation monitoring results for nine years after the accident at THE TEPCO Fukushima Daiichi Nuclear Power Plant at JAEA Oarai Research and Development Institute

Inoue, Yuki; Yamada, Junya; Maeda, Eita; Hatakeyama, Takumi; Miyauchi, Hideaki; Hashimoto, Makoto

no journal, , 

no abstracts in English

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