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Sato, Kazuyoshi; Omori, Junji; Kondoh, Takashi; Hatae, Takaki; Kajita, Shin*; Ishikawa, Masao; Neyatani, Yuzuru; Ebisawa, Katsuyuki*; Kusama, Yoshinori
Fusion Engineering and Design, 84(7-11), p.1713 - 1715, 2009/06
Times Cited Count:1 Percentile:10.21(Nuclear Science & Technology)Engineering analyses have been performed for the representative diagnostic upper port plug of ITER. Maintenance and integration design have been also carried out for the diagnostic components to be installed in the upper port plug. From the electromagnetic and structural analyses, it has come up an important problem to suppress the displacement of the upper port plug rather than to reduce the produced stress. Reducing the EM force will help to decrease the severity of potential displacement. Maximum displacement of the port plug decreases with increasing in the number of slits in a manner that the displacement would seem to be less than the design tolerance. A proposed low body roller and inner frame may enhance maintenance and integration. These studies and designs have established the design basis for the diagnostic upper port plug.
Sato, Koichi; Seki, Fumiko*; Hasegawa, Shiori*; Sengoku, Akio; Kitazawa, Sin-iti; Neyatani, Yuzuru; Koizumi, Koichi
JAEA-Data/Code 2008-019, 43 Pages, 2008/09
On October 24th, 2007, the Agreement on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project (the "ITER Agreement") came into force, and Japan Atomic Energy Agency (JAEA) was appointed to a Domestic Agency (DA). The DA will contribute to the ITER construction in cooperation with ITER Organization (IO) where many ITER-specific technical terms and abbreviations were used. This book is a collection of those terms and abbreviations translated to Japanese.
Sato, Kazuyoshi; Omori, Junji; Ebisawa, Katsuyuki*; Kusama, Yoshinori; Neyatani, Yuzuru
Plasma and Fusion Research (Internet), 2, p.S1088_1 - S1088_4, 2007/11
A part of diagnostic device in vacuum vessel is planned to install in the port plug to make sure the line of sight of diagnostics. Only basic concept is shown for the port plug since design of diagnostic devices has not been substantiated yet. The integration design of the port plug has been performed and the structure concept for electro-magnetic and neutron load has been investigated as for the No.11 upper port plug to confirm reliability of the proposed design. Three diagnostics will be installed in the No.11 upper port plug, the edge Thomson scattering system, the visible-IR TV divertor viewing system and the neutron activation system. To integrate theses diagnostic systems in the port plug, it was designed the arrangement of the labyrinth of optical path, the driving mechanism and cooling systems for shutters and mirrors, the maintenance space. The part just behind the blanket shield module (BSM) was changed to secure a space for maintenance and for associated diagnostic first mirror and shutter, whereas this place is assigned for neutron shielding in the present design. The BSM support, which is main component to apply the electro-magnetic load, was arranged with optical path inside BSM.
Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.
Journal of Nuclear Science and Technology, 44(3), p.441 - 447, 2007/03
Times Cited Count:9 Percentile:54.79(Nuclear Science & Technology)The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former have cutting installations for large size wastes and the latter have melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m and the volume reduction ratio is from 1.7 to 3.7. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005.
Sato, Kazuyoshi; Uehara, Masaharu*; Tamura, Kosaku*; Hashimoto, Masayoshi*; Ogino, Shunji*; Yagenji, Akira; Nagamatsu, Nobuhide*; Sekiya, Shigeki*; Takahashi, Hideo*; Motohashi, Keiichi*; et al.
JAEA-Technology 2006-024, 114 Pages, 2006/03
no abstracts in English
Sato, Kazuyoshi; Hashimoto, Masayoshi*; Nagamatsu, Nobuhide*; Yagenji, Akira; Sekiya, Shigeki*; Takahashi, Hideo*; Motohashi, Keiichi*; Ogino, Shunji*; Kataoka, Takahiro*; Ohashi, Hironori*; et al.
JAEA-Technology 2006-006, 587 Pages, 2006/03
no abstracts in English
Higuchi, Hidekazu; Momma, Toshiyuki; Nakashio, Nobuyuki; Kozawa, Kazushige; Tohei, Toshio; Sudo, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Ko; Ishikawa, Joji; et al.
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10
The JAERI constructed the Advanced Volume Reduction Facilities(AVRF). The AVRF consists of the Waste Size Reduction and Storage Facilities(WSRSF) and the Waste Volume Reduction Facilities(WVRF). By operating the AVRF, it will be able to produce waste packages for final disposal and to reduce the amount of the low level solid wastes. Cutting installations for large wastes such as tanks in the WSRSF have been operating since June 1999. The wastes treated so far amount to 600 m and the volume reduction ratio is around 1/3. The waste volume reduction is carried out by a high-compaction process or melting processes in the WVRF. The metal wastes from research reactors are treated by the high-compaction process. The other wastes are treated by the melting processes that enable to estimate radioactivity levels easily by homogenization and get chemical and physical stability. The WVRF have been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation with radioactive wastes will start in FY2005.
Mehmood, M.*; Kawaguchi, Nobuaki*; Maekawa, Hideki*; Sato, Yuzuru*; Yamamura, Tsutomu*; Kawai, Masayoshi*; Kikuchi, Kenji
Materials Transactions, 44(2), p.259 - 267, 2003/02
Times Cited Count:9 Percentile:52.01(Materials Science, Multidisciplinary)Electrochemical study has been carried out on the electro-deposition of tantalum in LiF-NaF-CaF melt containing KTaF at 700C. This has been done for determining the mechanistic features for preparing electrolytic coating of tantalum on nickel and tungsten substrates. Electro-deposition of metallic tantalum occurs primarily by electro-reduction of Ta(V). Pure metallic tantalum without any entrapped salt is successfully deposited on tungsten by galvanostatic polarization at reasonably low current densities. An additional feature on nickel is the formation of an intermetallic compound at potential 0.25V nobler than that of pure tantalum as a result of underpotential deposition of tantalum. This intermetallic compound covers the surface within a short time followed by deposition of pure tantalum, although intermetallic compound keeps growing at the interface of pure tantalum deposit and the substrate as a result of diffusion.
Sugie, Tatsuo; Hatae, Takaki; Koide, Yoshihiko; Fujita, Takaaki; Kusama, Yoshinori; Nishitani, Takeo; Isayama, Akihiko; Sato, Masayasu; Shinohara, Koji; Asakura, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.482 - 511, 2002/09
Times Cited Count:6 Percentile:3.03(Nuclear Science & Technology)The diagnostic system of JT-60U (JT-60upgrade) is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters have been improved, so that the internal structure of plasmas has been explored. The understanding of plasma confinement has been enhanced by density and temperature fluctuation measurements using a mm-wave reflectometer and electron cyclotron emission measurements respectively. In addition, the real-time control experiments of electron density, neutron yield, radiated power and electron temperature gradient have been carried out successfully by corresponding diagnostic devices. These measurements and the real time control contribute to improving plasma performance. Diagnostic devices for next generation fusion devices such as a CO2 laser interferometer/polarimeter and a CO2 laser collective Thomson scattering system have been developed.
Kamada, Yutaka; Fujita, Takaaki; Ishida, Shinichi; Kikuchi, Mitsuru; Ide, Shunsuke; Takizuka, Tomonori; Shirai, Hiroshi; Koide, Yoshihiko; Fukuda, Takeshi; Hosogane, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.185 - 254, 2002/09
Times Cited Count:34 Percentile:48.48(Nuclear Science & Technology)With the main aim of providing physics basis for ITER and the steady-state tokamak reactors, JT-60/JT-60U has been developing and optimizing the operational concepts, and extending the discharge regimes toward sustainment of high integrated performance in the reactor relevant parameter regime. In addition to achievement of the equivalent break-even condition (QDTeq up to 1.25) and a high fusion triple product = 1.5E21 m-3skeV, JT-60U has demonstrated the integrated performance of high confinement, high beta-N, full non-inductive current drive with a large fraction of bootstrap current in the reversed magnetic shear and in the high-beta-p ELMy H mode plasmas characterized by both internal and edge transport barriers. The key factors in optimizing these plasmas are profile and shape controls. As represented by discovery of various Internal Transport Barriers, JT-60/JT-60U has been emphasizing freedom and restriction of profiles in various confinement modes. JT-60U has demonstrated applicability of these high confinement modes to ITER and also clarified remaining issues.
Balucani, N.*; Algia, M.*; Cartechini, L.*; Casavecchia, P.*; Volpi, G. G.*; Sato, K.*; Takayanagi, Toshiyuki; Kurosaki, Yuzuru*
Journal of the American Chemical Society, 122(18), p.4443 - 4450, 2000/05
Times Cited Count:77 Percentile:87.92(Chemistry, Multidisciplinary)no abstracts in English
Sato, K.*; *; *; *; *; Kurosaki, Yuzuru*; Takayanagi, Toshiyuki
Chemical Physics, 242(1), p.1 - 10, 1999/00
Times Cited Count:7 Percentile:22.54(Chemistry, Physical)no abstracts in English
Takayanagi, Toshiyuki; Kurosaki, Yuzuru*; Yokoyama, Keiichi; Sato, K.*; *
Chemical Physics Letters, 312(5-6), p.503 - 510, 1999/00
Times Cited Count:9 Percentile:28.09(Chemistry, Physical)no abstracts in English
Takayanagi, Toshiyuki; Kurosaki, Yuzuru*; Sato, K.*; *; *; *
Journal of Physical Chemistry A, 103(2), p.250 - 255, 1999/00
Times Cited Count:34 Percentile:71.37(Chemistry, Physical)no abstracts in English
Sato, K.*; *; *; *; *; Kurosaki, Yuzuru*; Takayanagi, Toshiyuki
Journal of Physical Chemistry A, 103(43), p.8650 - 8656, 1999/00
Times Cited Count:27 Percentile:64.01(Chemistry, Physical)no abstracts in English
Kurosaki, Yuzuru*; Takayanagi, Toshiyuki; Sato, K.*; *
Journal of Physical Chemistry A, 102(1), p.254 - 259, 1998/00
Times Cited Count:52 Percentile:83.3(Chemistry, Physical)no abstracts in English
Takayanagi, Toshiyuki; Kurosaki, Yuzuru*; *; *; *; Sato, K.*; *
Journal of Physical Chemistry A, 102(31), p.6251 - 6258, 1998/00
Times Cited Count:42 Percentile:78.2(Chemistry, Physical)no abstracts in English
Takayanagi, Toshiyuki; Kurosaki, Yuzuru*; Sato, K.*; *
Journal of Physical Chemistry A, 102(50), p.10391 - 10398, 1998/00
Times Cited Count:29 Percentile:66.76(Chemistry, Physical)no abstracts in English
Hayashi, Hirokazu; Okamoto, Yoshihiro; Ogawa, Toru; Sato, Yuzuru*; Yamamura, Tsutomu*
Molten Salt Forum, 5-6, p.257 - 260, 1998/00
no abstracts in English
Kamada, Yutaka; Yoshino, Ryuji; Neyatani, Yuzuru; Sato, Masayasu; Tokuda, Shinji; Azumi, Masafumi; Takeji, Satoru; Ushigusa, Kenkichi; Fukuda, Takeshi; Mori, Masahiro; et al.
Plasma Physics and Controlled Nuclear Fusion, 38(8), p.1387 - 1391, 1996/08
Times Cited Count:45 Percentile:78.85(Physics, Fluids & Plasmas)no abstracts in English