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Journal Articles

Development of the backflow model for simplified impurity exhaust in Monte-Carlo calculation

Hoshino, Kazuo; Shimizu, Katsuhiro; Kawashima, Hisato; Takizuka, Tomonori*; Nakano, Tomohide; Ide, Shunsuke

Contributions to Plasma Physics, 54(4-6), p.404 - 408, 2014/06

 Times Cited Count:13 Percentile:33.25(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Assembly study for JT-60SA tokamak

Shibanuma, Kiyoshi; Arai, Takashi; Hasegawa, Koichi; Hoshi, Ryo; Kamiya, Koji; Kawashima, Hisato; Kubo, Hirotaka; Masaki, Kei; Saeki, Hisashi; Sakurai, Shinji; et al.

Fusion Engineering and Design, 88(6-8), p.705 - 710, 2013/10

 Times Cited Count:8 Percentile:36.72(Nuclear Science & Technology)

Journal Articles

Optimization of JT-60SA plasma operational scenario with capabilities of installed actuators

Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

Journal Articles

In-vessel tritium

Ueda, Yoshio*; Oya, Kaoru*; Ashikawa, Naoko*; Ito, Atsushi*; Ono, Tadayoshi*; Kato, Daiji*; Kawashima, Hisato; Kawamura, Gakushi*; Kenmotsu, Takahiro*; Saito, Seiki*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 88(9), p.484 - 502, 2012/09

no abstracts in English

Journal Articles

Evaluation of heat and particle controllability on the JT-60SA divertor

Kawashima, Hisato; Hoshino, Kazuo; Shimizu, Katsuhiro; Takizuka, Tomonori; Ide, Shunsuke; Sakurai, Shinji; Asakura, Nobuyuki

Journal of Nuclear Materials, 415(Suppl.1), p.S948 - S951, 2011/08

 Times Cited Count:6 Percentile:48.94(Materials Science, Multidisciplinary)

The divertor design of the JT-60SA tokamak device is finalized according to the engineering requirements and the physical analyses with the SONIC code simulations. Assuming the steady-state high beta core plasmas with 41 MW heating power, high heat and particle fluxes flowing out from core to SOL arrive at the divertor targets and give a large heat load. From the engineering viewpoint, the allowable heat load is restricted below 15 MW/m$$^{2}$$ by the tolerability of the target material and structure. As a scenario to reduce the heat load, the vertical target configuration is adopted to receive the heat load on the wide area. In addition, the V-shaped corner is set to enhance the recycling at the outer side divertor where receives a relatively large heat load. Then, the remote radiative cooling is optimized by control of the D$$_{2}$$ gas puffing, the impurity seeding and the divertor pumping.

Journal Articles

Plasma regimes and research goals of JT-60SA towards ITER and DEMO

Kamada, Yutaka; Barabaschi, P.*; Ishida, Shinichi; Ide, Shunsuke; Lackner, K.*; Fujita, Takaaki; Bolzonella, T.*; Suzuki, Takahiro; Matsunaga, Go; Yoshida, Maiko; et al.

Nuclear Fusion, 51(7), p.073011_1 - 073011_11, 2011/07

 Times Cited Count:53 Percentile:6.65(Physics, Fluids & Plasmas)

Journal Articles

An Outcome of nuclear safety research in JAERI; Case study for LOCA

Yanagisawa, Kazuaki; Ito, Keishiro*; Katsuki, Chisato*; Kawashima, Kei*; Shirabe, Masashi*

Scientometrics, 84(3), p.563 - 573, 2010/09

 Times Cited Count:3 Percentile:59.43(Computer Science, Interdisciplinary Applications)

no abstracts in English

JAEA Reports

Conceptual design of the SlimCS fusion DEMO reactor

Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.

JAEA-Research 2010-019, 194 Pages, 2010/08

JAEA-Research-2010-019-01.pdf:48.47MB
JAEA-Research-2010-019-02.pdf:19.4MB

This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m$$^{2}$$. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.

Journal Articles

Development of virtual private network for JT-60SA CAD integration

Oshima, Takayuki; Fujita, Takaaki; Seki, Masami; Kawashima, Hisato; Hoshino, Katsumichi; Shibanuma, Kiyoshi; Verrecchia, M.*; Teuchner, B.*

Journal of Plasma and Fusion Research SERIES, Vol.9, p.620 - 624, 2010/08

For interface control and assembly, the CAD data will be exchanged and integrated in a new Data Base server installed at Naka for JT-60SA, where a common computer network efficiently connected between the Naka site for JAEA and the Garching site for F4E is needed to be established. To ensure the design environments, a VPN (Virtual Private Network) was introduced with CAD LAN on computer network physically-separated from JAEA intranet area and firewall. In July 2009, a new VPN connection between the Naka and Garching sites has been successfully demonstrated using IPSec-VPN technology with a commercial and cost-effective firewall/router for security. The VPN technology would provide a common platform for the development of remote experimentation techniques on JT-60SA between Rokkasho and Naka in collaboration with activities of the ITER Remote Experimentation Centre for the IFERC Project at Rokkasho.

Journal Articles

Simulation of power exhaust in edge and divertor of the SlimCS tokamak demo reactor

Asakura, Nobuyuki; Shimizu, Katsuhiro; Kawashima, Hisato; Tobita, Kenji; Takizuka, Tomonori

Journal of Plasma and Fusion Research SERIES, Vol.9, p.136 - 141, 2010/08

Design of the power handling for the demo tokamak reactor, SlimCS (R = 5.5 m, R/a = 2.6) with the fusion power of 3 GW and the exhausted power of 500 MW was investigated. First results of the SONIC simulation (two dimensional plasma fluid code, i.e. SOLDOR, neutral Monte Carlo code, i.e. NEUT2D, and two dimensional impurity Monte Carlo code, i.e. IMPMC) of the edge and divertor plasmas with the intensive Ar seeding were presented. Distributions of the Ar ions and radiation loss are compared with those in the previous work with a constant impurity concentration of Ar (nAr/ni) and the non-coronal radiation model for the radiation power function. At the same time, heat loading to the divertor and the first wall is investigated in the radiative plasma operation of the demo reactor.

Journal Articles

Basic concept of JT-60SA tokamak assembly

Shibanuma, Kiyoshi; Arai, Takashi; Kawashima, Hisato; Hoshino, Katsumichi; Hoshi, Ryo; Kobayashi, Kaoru; Sawai, Hiroaki; Masaki, Kei; Sakurai, Shinji; Shibama, Yusuke; et al.

Journal of Plasma and Fusion Research SERIES, Vol.9, p.276 - 281, 2010/08

The JT-60 SA project is a combined project of JA-EU satellite tokamak program under the Broader Approach (BA) agreement and JA domestic program. Major components of JT-60SA for assembly are vacuum vessel (VV), superconducting coils (TF coils, EF coils and CS coil), in-vessel components such as divertor, thermal shield and cryostat. An assembly frame (with the dedicated cranes), which is located around the tokamak, is adopted to carry out effectively the assembly of tokamak components in the tokamak hall, independently of the facility cranes in the building. The assembly frame also provides assembly tools and jigs with jacks to support temporarily the components as well as to adjust the components at right positions. In this paper, the assembly scenario and scequence of the major components such as VV and TFC and the concept of the assembly frame including special jigs and fixtures are discussed.

JAEA Reports

An Outcome of nuclear safety research in JAERI; Predominance of research

Yanagisawa, Kazuaki; Kawashima, Kei*; Katsuki, Chisato*; Ito, Keishiro*

JAEA-Review 2009-050, 13 Pages, 2010/02

JAEA-Review-2009-050.pdf:6.63MB

Bibliometric study by means of research papers revealed the followings; (1) Nuclear Safety Research (NSR) performed in Japan is the 2nd highest in the world followed by USA. The share of JAERI for safety paper publication is about 25% in Japan (2) During past 25 years, JAERI is predominant at 39 safety fields out of 97, that is, 40% to the total. This is the fact revealed from comparison of published number of research papers with those of other organizations. (3) JAERI is recently changing its stress point from reactor-oriented accidents to the down stream of nuclear fuel cycling. There existed impact of TMI-2 accident on NSR-JAERI, especially in the field of thermal hydraulics, LOCA, severe accident and risk analysis.

Journal Articles

Tritium science and technology for fusion reactor, 3; Theory and code development for evaluation of tritium retention and exhaust in fusion reactor

Oya, Kaoru*; Inai, Kensuke*; Shimizu, Katsuhiro; Takizuka, Tomonori; Kawashima, Hisato; Hoshino, Kazuo; Hatayama, Akiyoshi*; Toma, Mitsunori*; Tomita, Yukihiro*; Kawamura, Gakushi*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 85(10), p.695 - 703, 2009/10

no abstracts in English

JAEA Reports

An Outcome of nuclear safety research in JAERI; Case study for LOCA, FP, criticality and reprocessing

Yanagisawa, Kazuaki; Ito, Keishiro*; Katsuki, Chisato*; Kawashima, Kei*; Shirabe, Masashi*

JAEA-Review 2009-022, 26 Pages, 2009/09

JAEA-Review-2009-022.pdf:17.62MB

An outcome of nuclear safety research done by JAERI was case studied by the bibliometric method. (1) For LOCA (loss-of-coolant accident) a domestic share of JAERI in monoclinic research paper was 63% at the past (20) 1978-1982 but was decreased to 40% at the present 1998-2002. For co-authored papers a domestic share between JAERI and PS (public sectors) is almost zero at past (20) but increased to 4% at the present. Research cooperation is active between Tokyo University and JAERI or between JAERI and Nagoya University. (2) Project-type research is to have a large monopolization in papers and that of basic-type research is to have a large DRN. (3)For reprocessing, PS had a monopolistic position with a domestic share of 71% and a share of JAERI was about 20%. (4) LOCA and RIA outputs born by NSR-JAERI coincided partly to those of the Safety Licensing Guidelines but a share of contribution done by JAERI was difficult to obtain due to the lack of necessary information.

Journal Articles

Integrated modeling for control of advanced tokamak plasma

Ozeki, Takahisa; Hayashi, Nobuhiko; Honda, Mitsuru; Aiba, Nobuyuki; Hamamatsu, Kiyotaka; Shimizu, Katsuhiro; Kawashima, Hisato; Hoshino, Kazuo; Takizuka, Tomonori; Tokuda, Shinji

Journal of Plasma and Fusion Research SERIES, Vol.8, p.1138 - 1142, 2009/09

Journal Articles

Spatial structure of volume recombination in JT-60U detached divertor plasmas

Fujimoto, Kayoko; Nakano, Tomohide; Kubo, Hirotaka; Sawada, Keiji*; Takizuka, Tomonori; Kawashima, Hisato; Shimizu, Katsuhiro; Asakura, Nobuyuki

Plasma and Fusion Research (Internet), 4, p.025_1 - 025_7, 2009/08

The volume recombination in detached divertor plasmas is a key process to reduce the ion flux to the divertor plates. Two-dimensional measurement is one of the ways to investigate a spatial structure of the volume recombination. In this work, the deuterium Balmer-series lines from a detached divertor plasma were observed two-dimensionally with a spatial resolution of 1 cm and were reconstructed into two-dimensional emissivities with a tomography technique. The ratio of the D$$_{beta}$$ to the D$$_{alpha}$$ emissivity was compared to that calculated by the collisional-radiative model. This ratio could not be explained only by the excitation of D by electron impact, indicating that the volume recombination contributed to the D$$_{beta}$$ emission. This is the case for the region above the inner strike point with 8 cm and 4 cm, respectively, in the r- and the z-direction on the poloidal cross-section.

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:119 Percentile:1.71(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

Study of fueling scenario and particle balance in a fusion reactor

Takenaga, Hidenobu; Kawashima, Hisato; Nishio, Satoshi; Tobita, Kenji

Fusion Science and Technology, 57(1), p.94 - 102, 2009/06

 Times Cited Count:5 Percentile:59.54(Nuclear Science & Technology)

A fuelling scenario in a fusion reactor has been investigated, where tritium is fuelled in the main plasma and deuterium is fuelled in both the main plasma and the edge plasma. The tritium fuelling in the main plasma minimizes the tritium fuelling rate necessary for sustaining the high tritium density in the main plasma, resulting in the minimum tritium recycling level at the fixed pumping fraction. The deuterium fuelling in the main plasma sustains the high deuterium density in the main plasma and the deuterium fuelling in the edge plasma enhances the deuterium recycling level for reducing the divertor temperature. Based on this scenario, particle balance was quantitatively investigated using the SlimCS design parameters at 2.95 GW fusion output with consideration of confinement times separately defined for the particles fuelled in the main plasma and the edge plasma.

Journal Articles

Design, R&D and assessment of performance of the JT-60SA upper divertor

Sakurai, Shinji; Kawashima, Hisato; Higashijima, Satoru; Shimizu, Katsuhiro; Masaki, Kei; Asakura, Nobuyuki; Shibama, Yusuke; Sakasai, Akira

Journal of Nuclear Materials, 390-391, p.891 - 894, 2009/06

 Times Cited Count:1 Percentile:88.49(Materials Science, Multidisciplinary)

The entire plasma facing components should be water-cooled in JT-60SA. A cassette module of divertor is introduced for remote maintenance. The divertor targets are mounted on the cassette. A brazed carbon fiber composite target is promising candidate for the divertor target. The latest results of mock-ups test clarified that thermal fatigue life cycles are more than 1000 cycles of 15 MW/m$$^{2}$$$$times$$10 sec. The divertor is designed to control divertor detachment for heat load reduction. The vertical targets and a "V-shaped corner" like as that in ITER are adopted to enhance detachment. Divertor heat load and pumping efficiency has been evaluated, using 2D plasma fluid (SOLDOR) and neutral Monte-Carlo (NEUT2D) code. The plasma detachment occurs near the outer-strike point within the "V-shaped corner", which results in low peak heat flux density 5.8 MW/m$$^{2}$$ for the case with additional gas puff of 5$$times$$10$$^{21}$$/s compared to 11.4 MW/m$$^{2}$$ for the case without "V-shaped corner".

Journal Articles

Radiation process of carbon ions in JT-60U detached divertor plasmas

Nakano, Tomohide; Kubo, Hirotaka; Asakura, Nobuyuki; Shimizu, Katsuhiro; Kawashima, Hisato; Higashijima, Satoru

Journal of Nuclear Materials, 390-391, p.255 - 258, 2009/06

 Times Cited Count:16 Percentile:23.25(Materials Science, Multidisciplinary)

Therefore it is concluded that the dominant radiator, C$$^{3+}$$, is produced by ionization of C$$^{2+}$$ and recombination of C$$^{4+}$$ at similar rates around the X-point in the detached plasma, and that C$$^{2+}$$ is the second biggest radiator. Further the transport loss of C$$^{3+}$$ will be investigated by an impurity transport code (IMPMC), in addition to comparison of the radiation power and atomic processes.

186 (Records 1-20 displayed on this page)