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Ioki, Kimihiro*; Elio, F.*; Maruyama, So; Morimoto, Masaaki*; Rozov, V.*; Tivey, R.*; Utin, Y.*
Fusion Engineering and Design, 74(1-4), p.185 - 190, 2005/11
Times Cited Count：5 Percentile：35.8(Nuclear Science & Technology)The ITER project has started preparation of Procurement Specification Documents for the vacuum vessel (VV). The design of the VV and FW/Blanket has progressed in many aspects, such as an double curvature pressing instead of facet shape welding for inner and outer shells in the upper and lower inboard regions to improve the fabrication and NDT process. The plasma facing surface of the FW has been defined to avoid protruding the leading edges, especially in the inboard area. Separate FW panels are supported with a central beam, and selection of a race-track shape cross-section for the central beam provides a more robust structure against halo current EM loads and also leads to a new cooling configuration in the shield block, where the pressure drop is significantly reduced to 
0.05 MPa. A UT R&D program is also going on to achieve acceptable S/N ratio for small-angle launching waves (20-30 deg.) to a weld. Hydraulic testing has been performed to demonstrate natural convection cooling in the transient condition.
Sekiguchi, Tetsuhiro; Baba, Yuji; Shimoyama, Iwao; Nath, K. G.
Journal of Electron Spectroscopy and Related Phenomena, 144-147, p.437 - 441, 2005/06
Times Cited Count：3 Percentile：17.62(Spectroscopy)no abstracts in English
Masaki, Kei
Nihon Genshiryoku Gakkai-Shi, 46(12), p.834 - 837, 2004/12
no abstracts in English
Ioki, Kimihiro*; Akiba, Masato; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Ezato, Koichiro; Federici, G.*; et al.
Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08
Times Cited Count：14 Percentile：66.09(Materials Science, Multidisciplinary)The preparation of the procurement specifications is being progressed for key components. Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive tests (NDT). R&D activities are being carried out on vacuum vessel UT inspection with waves launched at an angle of 20 or 30 degree, on flow distribution tests of a two-channel model, on fabrication and testing of FW mockups and panels, on the blanket flexible support as a complete system including the housing, on the blanket co-axial pipe connection with guard vacuum for leak detection, and on divertor vertical target prototypes. The results give confidence in the validity of the design and identify possibilities of attractive alternate fabrication methods.
Kurihara, Ryoichi
JAERI-Tech 2004-052, 39 Pages, 2004/07
The problems in the thermal structural design of the plasma facing component such as the blanket first wall and the divertor plate which receives very high heat flux were examined in the design of the fusion power reactors. Compact high fusion power reactor must give high heat flux and high-speed neutron flux from the plasma to the first wall and the divertor plate. In this environmental situation, the micro cracks should be generated in material of the first wall. Structural integrity of the first wall would be very low during the operation of the reactor, if those micro-cracks grow in a crack having significant size by the fatigue or the creep. The crack penetration in the first wall can be a factor which threatens the safety of the fusion power reactor. This paper summarizes the problems on the structural integrity in the first wall made of the SiC/SiC composite material or the ferritic steel.
Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.
Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12
Times Cited Count：101 Percentile：93.45(Physics, Fluids & Plasmas)no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Konishi, Satoshi; Sato, Masayasu; Tanabe, Tetsuo*; Masaki, Kei; Miya, Naoyuki
Fusion Engineering and Design, 65(4), p.561 - 568, 2003/07
Times Cited Count：20 Percentile：77.2(Nuclear Science & Technology)no abstracts in English
Ioki, Kimihiro*; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Gervash, A.*; Ibbott, C.*; Jones, L.*; et al.
Nuclear Fusion, 43(4), p.268 - 273, 2003/04
Times Cited Count：21 Percentile：54.59(Physics, Fluids & Plasmas)Although the basic concept of the vacuum vessel (VV) and in-vessel components of the ITER design has stayed the same, there have been several detailed design improvements resulting from efforts to raise reliability, to improve maintainability and to save money. One of the most important achievements in the VV R&D has been demonstration of the necessary fabrication and assembly tolerances. Recently the deformation due to cutting of the port extension was measured and it was shown that the deformation is small and acceptable. Further development of advanced methods of cutting, welding and NDT on a thick plate have been continued in order to refine manufacturing and improve cost and technical performance. With regard to the related FW/blanket and divertor designs, the R&D has resulted in the development of suitable technologies. Prototypes of the FW panel, the blanket shield block and the divertor components have been successfully fabricated.
D
) in JT-60UNakano, Tomohide; Higashijima, Satoru; Kubo, Hirotaka; Yagyu, Junichi; Arai, Takashi; Asakura, Nobuyuki; Itami, Kiyoshi
Journal of Nuclear Materials, 313-316(1-3), p.149 - 152, 2003/03
Times Cited Count：29 Percentile：85.65(Materials Science, Multidisciplinary)In JT-60U, boronization using hydride-decaborane (BD) was performed to reduce oxygen impurity and particle recycling. A problem of the boronization was that hydrogen originating from hydride-decaborane diluted core deuterium plasmas. In order to minimize the number of conditioning tokamak discharges, boronization using deuterated-decaborane (BD) has been introduced recently. In order to investigate durability of the boronization effects, discharges with an identical condition were repeated. Boronization using 20 g of deuterated-decaborane could reduce a core oxygen content from 1.9% to only 1.3% in L-mode discharges with a neutral beam heating power of 4 MW. Boronization using 70 g of deuterated-decaborane reduced the core oxygen content from 2.2% to 0.5%. After the boronization using 70 g of deuterated-decaborane ( thickness of the Boron layer 135 nm ), the core oxygen content increased gradually from 0.5% to 1% in 400 shots.
Kuroda, Toshimasa*; Hatano, Toshihisa; Miki, Nobuharu*; Hiroki, Seiji; Enoeda, Mikio; Omori, Junji*; Sato, Shinichi*; Akiba, Masato
JAERI-Tech 2002-098, 136 Pages, 2003/02
JAERI-Tech-2002-098.pdf:24.33MB
no abstracts in English
Higashijima, Satoru; Nakamura, Hirofumi; Horikawa, Toyohiko*; Kaminaga, Atsushi; Seki, Masami; Kubo, Hirotaka; Konishi, Satoshi; Tanabe, Tetsuo*
Proceedings of 30th EPS Conference on Controlled Fusion and Plasma Physics (CD-ROM), 4 Pages, 2003/00
no abstracts in English
Hatano, Toshihisa; Kuroda, Toshimasa*; Barabash, V.*; Enoeda, Mikio
Journal of Nuclear Materials, 307-311(2), p.1537 - 1541, 2002/12
Times Cited Count：4 Percentile：29.25(Materials Science, Multidisciplinary)no abstracts in English
Uchida, Munenori*; Ishitsuka, Etsuo; Hatano, Toshihisa; Barabash, V.*; Kawamura, Hiroshi
Journal of Nuclear Materials, 307-311(Part2), p.1533 - 1536, 2002/12
Times Cited Count：3 Percentile：23.41(Materials Science, Multidisciplinary)no abstracts in English
Ioki, Kimihiro*; Akiba, Masato; Cardella, A.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Lorenzetto, P.*; Miki, Nobuharu*; Osaki, Toshio*; Rozov, V.*; et al.
Fusion Engineering and Design, 61-62, p.399 - 405, 2002/11
Times Cited Count：11 Percentile：58.11(Nuclear Science & Technology)We report progress on the ITER-FEAT Blanket design and R&D during 2001-2002. Four major sub-components (FW, shield body, flexible support and electrical connection) have been highlighted. Regarding the FW, design on a separate FW panel concept has progressed, and heat load tests on a small-scale mock-up have been successfully performed with 0.7 MW/m
, 13000 cycles. Full-scale separate FW panels (dimensions: 0.9
0.250.07 m) have been fabricated by HIPing and brazing. Regarding the shield body, a radial flow cooling design has been developed, and full-scale partial mock-ups have been fabricated by using water-jet cutting. A separate FW panel was assembled with one the shield body mock-ups. Regarding the flexible support, mill-annealed Ti (easier fabricability) alloy has been selected, and the remote assembly has been considered in the design. In mechanical tests, the requires buckling strength and mechanical fatigue characteristics have been confirmed. Regarding the electrical connection, one-body structure design without welding joints has been developed. Mechanical fatigue tests in the 3 directions, have been carried out, and thermal fatigue tests and electrical tests in a solenoidal magnetic field have been performed. Feasibility of the design has been confirmed. Through progress on design and R&D of the blanket, cost reduction has been achieved, and feasibility of design and fabricability of the components have been confirmed.
Bakhtiari, M.; Kawano, Yasunori; Tamai, Hiroshi; Miura, Yushi; Yoshino, Ryuji; Nishida, Yasushi*
Nuclear Fusion, 42(10), p.1197 - 1204, 2002/10
Times Cited Count：49 Percentile：80.12(Physics, Fluids & Plasmas)no abstracts in English
Kawashima, Hisato; Tsuzuki, Kazuhiro; Tani, Takashi; Sato, Masayasu; Suzuki, Sadaaki; Kimura, Haruyuki
Purazuma, Kaku Yugo Gakkai-Shi, 78(9), p.935 - 940, 2002/09
no abstracts in English
Kawamura, Hiroshi
JAERI-Review 2002-011, 165 Pages, 2002/06
JAERI-Review-2002-011.pdf:28.71MB
no abstracts in English
Tamai, Hiroshi; Yoshino, Ryuji; Tokuda, Shinji; Kurita, Genichi; Neyatani, Yuzuru; Bakhtiari, M.; Khayratdinov, R. R.*; Lukash, V.*; Rosenbluth, M. N.*; JT-60 Team
Nuclear Fusion, 42(3), p.290 - 294, 2002/03
Times Cited Count：34 Percentile：70.69(Physics, Fluids & Plasmas)no abstracts in English
Yagyu, Junichi; Arai, Takashi; Kaminaga, Atsushi; Kizu, Kaname; Arai, Masaru*; Miya, Naoyuki
Proceedings of 19th IEEE/NPSS Symposium on Fusion Engineering (SOFE), p.388 - 391, 2002/00
no abstracts in English
