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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.

JAEA Reports

Studies on grouting performance in Mizunami Underground Research Laboratory (Contract research)

Kawamura, Hideki*; Ando, Kenichi*; Noda, Masaru*; Tanaka, Tatsuya*; Matsuda, Takeshi*; Fujii, Haruhiko*; Hashimoto, Shuji*; Ueda, Tadashi*; Matsui, Hiroya; Takeuchi, Shinji; et al.

JAEA-Technology 2009-081, 182 Pages, 2010/03

JAEA-Technology-2009-081.pdf:28.89MB

Grouting has practical importance for the reduction of groundwater inflow into excavations during construction of underground facilities. Considering the performance assessment of a radioactive waste repository, the performance of the engineered barrier system could be adversely affected by a high pH plume generated from grout. Therefore, a quantitative estimation of the effectiveness of grouting and grout material is essential. This study has been performed in the Mizunami URL being excavated in crystalline rock as a part of the Project for Grouting Technology Development for the Radioactive Waste Repository funded by METI, Japan. The aims were to evaluate the applicability of existing grouting technology and to develop methodology to determine the distribution of grout and change in hydraulic properties of the grouted rock volume. The target rock is the volume of rock around a planned refuge niche where the pre-excavation grouting was performed at 200-m depth from ground surface. After excavation of the refuge niche, ten boreholes were drilled and different kinds of investigations were carried out during and after drilling. The results were integrated and groundwater flow analysis of pre and post excavation grouting conditions were carried out to estimate quantitatively the effect of pre-excavation grouting. The results suggest that current pre-excavation grouting technology is effective for reduction of groundwater inflow into excavations and that hydraulic conductivity of the surrounding rock can be reduced by more than one order of magnitude.

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:118 Percentile:1.69(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 on grouting performance for underground construction in crystalline rock, 3; Numerical simulation of water-tightness improvement

Tanaka, Tatsuya*; Matsui, Hiroya; Hashimoto, Shuji*; Ando, Kenichi*; Takeuchi, Shinji; Saegusa, Hiromitsu

Dai-38-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koen Rombunshu (CD-ROM), p.143 - 148, 2009/01

This study aims to establish techniques for grouting, and evaluation of the effects of grouting on the geological environment, to be applied in the field of high level radioactive waste disposal in the deep underground. A block-scale hydrogeological model has been generated using discrete fracture networks based on data obtained from the short-borehole investigation campaign performed at the research tunnel around which grouting has been carried out. The grouting performance in terms of reducing the water inflow rate was evaluated by groundwater flow simulation. Lessons learned applicable to future studies of in-situ testing have been addressed.

Journal Articles

Study on grouting performance in the Mizunami Underground Research Laboratory; Modification and application of hydraulic test for grouting

Ando, Kenichi*; Takeuchi, Shinji; Matsui, Hiroya; Tanaka, Tatsuya*; Hashimoto, Shuji*; Fujii, Haruhiko*

Dai-38-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koen Rombunshu (CD-ROM), p.137 - 142, 2009/01

Evaluation of the effect of grouting on the geological environment is important for quality control of the design and management of the construction of underground facilities for high level radioactive waste disposal. Lugeon test has been commonly used to check the hydraulic characteristics around borehole whether or not to inject grout in Japan. The aim of this study is to develop a hydraulic test which can be applied to obtain hydraulic conductivities of low permeable rockmass (e.g. 10$$^{-7}$$ to 10$$^{-9}$$m/s) during grouting. The proposed hydraulic test with the test sequence of water injection and pressure recovery has been carried out in Mizunami URL excavated in crystalline rock. The developed type curve matching methodologies have been applied to evaluate hydraulic conductivity in-situ in a simple manner. Lessons learned for future application for grouting have been addressed.

Journal Articles

Hydraulic tomography in fractured granite; The Mizunami Underground Research Site, Japan

Illman, W.*; Liu, X.*; Takeuchi, Shinji; Yeh, J.*; Ando, Kenichi*; Saegusa, Hiromitsu

Water Resources Research, 45, p.W01406_1 - W01406_18, 2009/00

 Times Cited Count:123 Percentile:18.03(Environmental Sciences)

Two large-scale cross-hole pumping tests were conducted at separate locations in deep boreholes at the Mizunami Underground Research Laboratory (MIU) construction site in central Japan. We analyze the two cross-hole tests using the transient hydraulic tomography (THT) code to compute the hydraulic conductivity ($$K$$) and specific storage ($$S$$$$_{s}$$) tomograms, as well as their uncertainties in three-dimensions. The equivalent $$K$$ and $$S$$$$_{s}$$ obtained using asymptotic analysis served as the initial parameter estimates for the 3D stochastic inverse modeling effort. Results show several, distinct high $$K$$ and low $$S$$$$_{s}$$ zones that are continuous over hundreds of meters, which appear to delineate fault zones and their connectivity. The THT analysis of the tests also identified a low $$K$$ zone which corresponds with a known fault zone trending NNW and has been found to compartmentalize groundwater flow at the site. These results corroborate well with several hydrogeological phenomena around the site.

Journal Articles

Conceptual design of magnet system for JT-60 super advanced (JT-60SA)

Kizu, Kaname; Tsuchiya, Katsuhiko; Ando, Toshinari*; Sborchia, C.*; Masaki, Kei; Sakurai, Shinji; Sukegawa, Atsuhiko; Tamai, Hiroshi; Fujita, Takaaki; Matsukawa, Makoto; et al.

IEEE Transactions on Applied Superconductivity, 17(2), p.1348 - 1352, 2007/06

 Times Cited Count:4 Percentile:68.61(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Study on the methodology for hydrogeological site descriptive modelling by discrete facture networks

Tanaka, Tatsuya*; Ando, Kenichi*; Hashimoto, Shuji*; Saegusa, Hiromitsu; Takeuchi, Shinji; Amano, Kenji

Dai-36-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koen Rombunshu (CD-ROM), p.267 - 272, 2007/01

no abstracts in English

Journal Articles

Study of evaluation for hydraulic properties with the single borehole-Hydraulic test

Hashimoto, Shuji*; Tanaka, Tatsuya*; Ando, Kenichi*; Takeuchi, Shinji; Saegusa, Hiromitsu; Kim, H.*

Dai-36-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koen Rombunshu (CD-ROM), p.419 - 424, 2007/01

no abstracts in English

Journal Articles

Poloidal field coil configuration and plasma shaping capability in NCT

Matsukawa, Makoto; Tamai, Hiroshi; Fujita, Takaaki; Kizu, Kaname; Sakurai, Shinji; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; Ando, Toshinari; Miura, Yushi

IEEE Transactions on Applied Superconductivity, 16(2), p.914 - 917, 2006/06

 Times Cited Count:4 Percentile:68.95(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Design study of fusion DEMO plant at JAERI

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Sato, Masayasu; Isono, Takaaki; Sakurai, Shinji; Nakamura, Hirofumi; Sato, Satoshi; Suzuki, Satoshi; Ando, Masami; et al.

Fusion Engineering and Design, 81(8-14), p.1151 - 1158, 2006/02

 Times Cited Count:110 Percentile:0.73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

 Times Cited Count:7 Percentile:74.43(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

 Times Cited Count:2 Percentile:92.8(Physics, Fluids & Plasmas)

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-$$beta$$. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

 Times Cited Count:2 Percentile:81.95(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

Journal Articles

Engineering design study of JT-60 superconducting modification

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Kurita, Genichi; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ichige, Hisashi; Kaminaga, Atsushi; Kato, Takashi; et al.

Proceedings of 19th IEEE/NPSS Symposium on Fusion Engineering (SOFE), p.221 - 225, 2002/00

no abstracts in English

JAEA Reports

Measurements of differential cross sections for the reactions $$^{6,7}$$Li(n,d)$$^{5.6}$$He and $$^{6,7}$$Li(n,t)$$^{4,5}$$He at 14.1 MeV

Shirato, Shoji*; Shibuya, Shinji*; Hata, Kazuhiro*; Ando, Yoshiaki*; Shibata, Keiichi

JAERI-M 89-107, 27 Pages, 1989/08

JAERI-M-89-107.pdf:0.75MB

no abstracts in English

Oral presentation

Three-dimensional inverse modeling of two large-scale cross-hole hydraulic tests in fractured granite at the Mizunami Underground Research Laboratory site, Japan

Illman, W.*; Liu, X.*; Yeh, J.*; Ando, Kenichi*; Takeuchi, Shinji; Saegusa, Hiromitsu

no journal, , 

Two cross-hole tests were conducted at separate locations in deep boreholes at the MIU construction site in central Japan. We analyze the two cross-hole hydraulic tests using the Transient Hydraulic Tomography (THT) code of Zhu and Yeh [2005] to compute the hydraulic conductivity (K) and specific storage (Ss) distributions as well as their uncertainties in three-dimensions. The equivalent K and Ss were obtained using the asymptotic analysis served as the initial parameter estimates for the 3D stochastic inverse modeling effort. Results show 2 distinct high K and low Ss zones that are continuous over distances ranging from 550 - 1,200 m, which delineate 2 separate fault zones. The fault zones that are imaged through THT correlate well with available geological data and drawdown records. The analysis of the tests with the THT code also identified a low K zone which corresponds with a known fault zone trending NNW and has been found to compartmentalize groundwater flow at the site.

Oral presentation

Re-interpretation of the fluid electric conductivity measurements carried out in the MIZ-1 borehole at the Mizunami Underground Research Laboratory project

Bruines, P.*; Ando, Kenichi*; Niibori, Yuichi*; Matsuoka, Kiyoyuki*; Takeuchi, Shinji

no journal, , 

Fluid electric conductivity (FEC) measurements have been carried out in the 1,350 m long MIZ-1 borehole followed by the modeling of FEC curve with newly developed finite difference code and obtaining tranmissivity in each feed point from FEC logging. The obtained results are comparable to those obtained by hydraulic testing. The method can be valuable to help in the selection of locations for more detailed hydraulic tests. Under certain circumstances the method can be used as a low cost alternative to hydraulic testing.

Oral presentation

Results of winding trial for ITER TF coil

Matsui, Kunihiro; Yamane, Minoru; Hemmi, Tsutomu; Kajitani, Hideki; Takano, Katsutoshi; Ando, Shinji; Koizumi, Norikiyo

no journal, , 

no abstracts in English

34 (Records 1-20 displayed on this page)