Actively circulated liquid metal divertor (ACLMD)

Shimada, Michiya; Hirooka, Yoshihiko*; Zhou, H.*

Europhysics Conference Abstracts (Internet), 38F, p.O2.110_1 - O2.110_4, 2014/00

http://ocs.ciemat.es/EPS2014PAP/pdf/O2.110.pdf

Tungsten is considered to be most promising candidate for divertor target material for fusion reactor. Although tungsten target can withstand the heat loads of ITER, the heat exhaust requirement for DEMO is much more demanding. Pulsive heat loads associated with disurption would melt the tungsten divertor target. Melting and subsequent resolidification will roughen the tungsten surface, significantly deteriorating the heat handling capability. Further, tungsten has a rather high DBTT (Ductile-Brittle-Transition temperature) of 400C. Neutron irradiation would further increase the DBTT, which could result in cracks. In view of these issues, liquid metal divertor is proposed, which is actively circulated with the Lorentz force introduced through the electrodes in the liquid metal. A modest flow speed of 0.3 m/s seems to be adequate for the heat load exhaust of DEMO. A simple treatment of MHD equation in a cylindrical geometry suggests that the requirements on the current and voltage are modest if the ramp-up of current is made slowly (e.g. in a minute), implying that the this concept is worth further study.

Recent progress in the energy recovery linac project in Japan

Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05

http://accelconf.web.cern.ch/AccelConf/IPAC10/papers/tupe091.pdf

Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.

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

https://doi.org/10.1093/nar/gkm999

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.

Progress in the ITER physics basis, 1; Overview and summary

Shimada, Michiya; Campbell, D. J.*; Mukhovatov, V.*; Fujiwara, Masami*; Kirneva, N.*; Lackner, K.*; Nagami, Masayuki; Pustovitov, V. D.*; Uckan, N.*; Wesley, J.*; et al.

Nuclear Fusion, 47(6), p.S1 - S17, 2007/06

https://doi.org/10.1088/0029-5515/47/6/S01

The Progress in the ITER Physics Basis document is an update of the ITER Physics Basis (IPB), which was published in 1999. The IPB provided methodologies for projecting the performance of burning plasmas, developed largely through coordinated experimental, modeling and theoretical activities carried out on today's tokamaks (ITER Physics R&D). In the IPB, projections for ITER (1998 Design) were also presented. The IPB also pointed out some outstanding issues. These issues have been addressed by the International Tokamak Physics Activities (ITPA), which were initiated by the European Union, Japan, Russia and the U.S.A.. The new methodologies of projection and control developed through the ITPA are applied to ITER, which was redesigned under revised technical objectives, but will nonetheless meet the programmatic objective of providing an integrated demonstration of the scientific and technological feasibility of fusion energy.

Progress in physics basis and its impact on ITER

Shimada, Michiya; Campbell, D.*; Stambaugh, R.*; Polevoi, A. R.*; Mukhovatov, V.*; Asakura, Nobuyuki; Costley, A. E.*; Donn, A. J. H.*; Doyle, E. J.*; Federici, G.*; et al.

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

This paper summarises recent progress in the physics basis and its impact on the expected performance of ITER. Significant progress has been made in many outstanding issues and in the development of hybrid and steady state operation scenarios, leading to increased confidence of achieving ITER's goals. Experiments show that tailoring the current profile can improve confinement over the standard H-mode and allow an increase in beta up to the no-wall limit at safety factors 4. Extrapolation to ITER suggests that at the reduced plasma current of 12MA, high Q 10 and long pulse (1000 s) operation is possible with benign ELMs. Analysis of disruption scenarios has been performed based on guidelines on current quench rates and halo currents, derived from the experimental database. With conservative assumptions, estimated electromagnetic forces on the in-vessel components are below the design target values, confirming the robustness of the ITER design against disruption forces.

Study on the Corrosion Behavior of the Overpack Material in the Buffer Environment(II)

Suzuki, H.*; Hata, Yuji*; Shimada, T.*; Yamada, M.*

JNC TJ8400 2003-027, 125 Pages, 2002/03

JNC-TJ8400-2003-027.pdf:13.32MB

Laboratory scale test was conducted in order to investigate the corrosion behavior of carbon steel overpack material by simulating gaps between buffer materials, which are supposed to be generated when the buffer material is set in the disposal facility. Fifty-eight day tests were performed under various aqueous solutions in the buffer material by changing the pH of the solutions and the width of the gaps simulated. The longer period of 150 day test was also conducted, and the data on the corrosion behavior of the overpack carbon steel were obtained. Based on the test results such as corrosion rates, depth profiles, electrode potential etc. of the carbon steel test specimens, the corrosion behavior was discussed taking into account of the aqueous solution environment and the gap width of the buffer material. As a test result, the influence of the gap width of the buffer material was very little and the higher pH condition of the aqueous solutions as being contact with cement gave the higher corrosion rate to the carbon steel than the ordinary seawater. The extent of local corrosion in the present test was compared with those of the former reports. The result showed the extent of the local corrosion, a ratio of maximum and average depth, was not influenced by the width of the gap between buffer material or by the aqueous environment. All the ratios obtained in the present study were below or within the data band of the former data taken in the various aqueous conditions and natural soils, implying that the corrosion safety was preserved even when the gaps were generated between the buffer materials. Furthermore, problems of the laboratory scale test and needs for a large scale test were also discussed.

Spin-resolved core-level photoemission spectra of ferromagnetic nickel

Saito, Yuji; Suga, Shigemasa*; Kakizaki, A.*; Matsushita, T.*; Imada, S.*; Daimon, H.*; Ono, Kanta*; Fujisawa, M.*; Kinoshita, T.*; Ishii, T.*; et al.

Journal of Electron Spectroscopy and Related Phenomena, 78, p.329 - 332, 1996/05

https://doi.org/10.1016/S0368-2048(96)80091-0

no abstracts in English

The Design of the 8 GeV synchrotron and the beam transport system

Shimada, Taihei; Kabasawa, M.*; Nakayama, K.*; Hashimoto, H.*; Harami, Taikan; Suzuki, Hiromitsu

Proceedings of the 7th Symposium on Accelerator Science and Technology, p.305 - 308, 1989/00

The synchrotron and the beam transport lines have been designed. These are used as a part of the injection system for the 8 GeV storage ring of SPring-8. To keep high injection-efficiency into the storage ring, the emittance of the beam is designed to be smaller than 200 nm rad and transverse phase-space matching is made at the injection point of the ring. The calculation about the beam transport lines and the synchrotron is performed using the code SYNCH.

Benchmark study of some thermal and structural computer codes for nuclear shipping casks

; Nanae, Y.*; Shimada, H.*; Shimada, A.*

Nihon Genshiryoku Gakkai-Shi, 26(9), p.781 - 792, 1984/00

https://doi.org/10.3327/jaesj.26.781

no abstracts in English