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Journal Articles

Comparison of transient electron heat transport in LHD helical and JT-60U tokamak plasmas

Inagaki, Shigeru*; Takenaga, Hidenobu; Ida, Katsumi*; Isayama, Akihiko; Tamura, Naoki*; Takizuka, Tomonori; Shimozuma, Takashi*; Kamada, Yutaka; Kubo, Shin*; Miura, Yukitoshi; et al.

Nuclear Fusion, 46(1), p.133 - 141, 2006/01

 Times Cited Count:55 Percentile:85.19(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Comparison of transient electron heat transport in LHD helical and JT-60U tokamak plasmas

Inagaki, Shigeru*; Takenaga, Hidenobu; Ida, Katsumi*; Isayama, Akihiko; Tamura, Naoki*; Takizuka, Tomonori; Shimozuma, Takashi*; Kamada, Yutaka; Kubo, Shin*; Miura, Yukitoshi; et al.

Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11

no abstracts in English

JAEA Reports

Long-term effect of creep displacement of host-rock on stability of engineered barrier system for TRU waste; Two-dimensional analysis by the non-linear viscoelasticity model

Aoyagi, Takayoshi*; *; Mihara, Morihiro; Okutsu, Kazuo*; Maeda, Munehiro*

JNC TN8400 2001-024, 103 Pages, 2001/06

JNC-TN8400-2001-024.pdf:8.84MB

In the disposal concept of TRU waste, concentrated disposal of wastes forms in large cross-section underground cavities is envisaged, because most of TRU waste is no-heat producing in spite of large generated volume as compared with HLW. In the design of engineered barrier system based on large cross-section cavities, it is necessary to consider the long-term mechanical process such as creep displacement of the host rock from the viewpoint of the stability of engineered barrier system. In this study, the long-term creep displacement of the host rock was calculated using the non-linear viscoelasticity model and the effects on the stability of engineered barrier system was evaluated. As a result, in the disposal concept of crystalline rock, no creep displacement occurred at the time after 1 milion year. On the other hand, in the disposal concept of sedimentary rock, creep displacement of 80$$sim$$90mm occurred at the time after 1 milion year. Also, in this calculation, a maximum reduction of 45mm concerned with the thickness of buffer material was estimated. But these values resulted within allowance of design values. Therefore, these results show that the effects of the creep displacement on the stability of engieered barrier system would not be significant.

Journal Articles

Theoretical analysis on phototimulated luminescence phenomenon of imaging plate

Kishimoto, Maki; Nakamura, Tatsuya; To, Kentaro; Sakasai, Kaoru; Katagiri, Masaki; Takahashi, Hiroyuki*; Nakazawa, Masaharu*

Nihon Genshiryoku Gakkai-Shi, 43(2), p.168 - 181, 2001/02

 Times Cited Count:1 Percentile:11.99(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Performance evaluation on reactor power control by H$$^{infty}$$ controller with gain scaling

Ishikawa, Nobuyuki; Suzuki, Katsuo

JAERI-Research 97-038, 17 Pages, 1997/05

JAERI-Research-97-038.pdf:0.56MB

no abstracts in English

Journal Articles

Qualitative analysis of nonlinear power oscillation in NSRR

Suzudo, Tomoaki; Shinohara, Yoshikuni

Annals of Nuclear Energy, 21(5), p.291 - 301, 1994/00

 Times Cited Count:2 Percentile:28.05(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Proportional-integral control modes for a hydrogen isotope distillation column

; J.R.Bortlit*; R.H.Sherman*

Nucl.Technol./Fusion, 5, p.30 - 41, 1984/00

no abstracts in English

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