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Journal Articles

Electronic structure of EuAl$$_4$$ studied by photoelectron spectroscopy

Kobata, Masaaki; Fujimori, Shinichi; Takeda, Yukiharu; Okane, Tetsuo; Saito, Yuji; Kobayashi, Keisuke*; Yamagami, Hiroshi; Nakamura, Ai*; Hedo, Masato*; Nakama, Takao*; et al.

Journal of the Physical Society of Japan, 85(9), p.094703_1 - 094703_6, 2016/09

 Times Cited Count:13 Percentile:62.55(Physics, Multidisciplinary)

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

 Times Cited Count:137 Percentile:97.72(Physics, Fluids & Plasmas)

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m$$^{2}$$ or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

Journal Articles

The H-Invitational Database (H-InvDB); A Comprehensive annotation resource for human genes and transcripts

Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.

Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01

 Times Cited Count:51 Percentile:71.25(Biochemistry & Molecular Biology)

Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.

Oral presentation

Water-cooled solid breeding blanket design for DEMO

Tobita, Kenji; Saito, Ai*; Nishio, Satoshi; Enoeda, Mikio; Tanigawa, Hisashi; Sato, Satoshi; Tsuru, Daigo; Hirose, Takanori; Seki, Yohji; Yamada, Masao*

no journal, , 

Self-sufficiency of tritium fuel is an indispensable requirement in a fusion reactor. In this sense, the blanket design ensuring the self-sufficiency of fuel should be considered with importance and higher priority in fusion reactor design. Generally speaking, however, it is difficult to envisage a self-consistent blanket design satisfying various requirements such as robustness to an enormous electromagnetic forces and excellent heat removal performance other than fuel self-sufficiency with matured candidate materials. This paper presents a concept study on torus configuration with water-cooled solid breeder blanket satisfying these functions. The result indicates that (1) the conducting shell should be arranged at the position of r$$_{w}$$/a =1.34 or farther, and (2) when blanket is installed behind the divertor, the increment of tritium breeding ratio is as low as 0.01-0.02. In addition, promising blanket concepts in the presently studied DEMO reactor are proposed.

Oral presentation

Blanket neutronics design on fusion DEMO reactor, SlimCS

Saito, Ai*; Tobita, Kenji; Nishio, Satoshi; Sato, Satoshi; Enoeda, Mikio

no journal, , 

Based on the combined analysis with neutronics and heat transfer, blanket concept of a fusion DEMO reactor named SlimCS was studied. The study indicates that satisfying tritium self-sufficiency and heat removal simultaneously is difficult as long as water-cooled solid breeder blanket is concerned. The most highest tritium breeding ratio (TBR) was obtained for a separated arrangement with Li$$_{2}$$TiO$$_{3}$$ pebbles and Be plates. However, this concept has a disadvantage in a complexity of the internal structure. When the mixed packing of Li$$_{2}$$TiO$$_{3}$$ and Be$$_{12}$$Ti pebbles is applied, the internal structure of blanket becomes simple but tritium self-sufficiency seems problematic adversely. Issues in these blanket study and possible solutions are presented.

Oral presentation

Electronic structure of EuAl$$_4$$ studied by SX-ARPES

Kobata, Masaaki; Fujimori, Shinichi; Takeda, Yukiharu; Okane, Tetsuo; Saito, Yuji; Kobayashi, Keisuke*; Yamagami, Hiroshi; Nakamura, Ai*; Hedo, Masato*; Nakama, Takao*; et al.

no journal, , 

no abstracts in English

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