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Nishino, Saki; Tsuboi, Masatoshi; Okada, Jumpei; Saegusa, Yu; Omori, Kazuki; Yasuo, Kiyoshi; Seshimo, Kazuyoshi; Domura, Kazuyuki; Yamamoto, Masahiko
Nihon Hozen Gakkai Dai-17-Kai Gakujutsu Koenkai Yoshishu, p.541 - 548, 2021/07
no abstracts in English
Omori, Junji; Koizumi, Norikiyo; Shimizu, Tatsuya; Okuno, Kiyoshi; Hasegawa, Mitsuru*
JAEA-Technology 2009-046, 60 Pages, 2009/09
JAEA-Technology-2009-046.pdf:9.67MB
In the winding pack (WP) of the ITER TF coil, cover plates (CPs) are welded to radial plate (RP) after placing the conductors into the RP groove to fix it. The dimensions of the RP are 15 m high and 9 m wide, while its required tolerances are very severe such as flatness of 2 mm and in-plane deformation of about 2.5 mm. It is therefore necessary to reduce the deformation of the RP by CP welding. In order to estimate the weld deformation, a 1 m RP mock-up was fabricated and weld deformations were measured. From the test results, inherent strains have been obtained and the weld deformations of the full scale RP have been estimated. The RP deformations could be within the tolerances by the CP welding thickness of 2.5 mm in inboard region and 1.0 mm in outboard region. In addition, an alternative design, which improve the fabricability of the WP, was proposed. The analyses for the alternative design is performed and the results show the deformations could be reduced more.
Shimizu, Katsusuke*; Onozuka, Masanori*; Usui, Yukinori*; Urata, Kazuhiro*; Tsujita, Yoshihiro*; Nakahira, Masataka; Takeda, Nobukazu; Kakudate, Satoshi; Omori, Junji; Shibanuma, Kiyoshi
Fusion Engineering and Design, 82(15-24), p.2081 - 2088, 2007/10
Times Cited Count：5 Percentile：37.19(Nuclear Science & Technology)To confirm the manufacturing and assembly process of the ITER vacuum vessel (VV), a series of related tests has been conducted. (1) Using a full-scale partial mock-up, fabrication methods are to be examined to determine feasibility. (2) To simulate a series of field-joint assembly operations, a test stand was built. (3) To provide an appropriate shield gas supply on the back side of the outer shell during field-joint welding, three types of back-seal structures have been tested. (4) The applicability of UT methods for volumetric inspection has been investigated. (5) Applicability of Liquid Penetrant Testing as a surface examination for the VV interior surface (i.e. ultra-vacuum side) has been investigated.
Omori, Junji; Nakahira, Masataka; Takeda, Nobukazu; Shibanuma, Kiyoshi; Sago, Hiromi*; Onozuka, Masanori*
JAEA-Technology 2006-017, 134 Pages, 2006/03
JAEA-Technology-2006-017.pdf:15.96MB
In order to improve the fabricability of the vacuum vessel (VV) of International Thermonuclear Experimental Reactor (ITER), applicability of plug weld between VV outer shell and stiffening ribs/blanket support housings has been assessed using crack propagation analysis for the plug weld. The ITER VV is a double-wall structure of inner and outer shells with ribs and housings between the shells. For the fabrication of VV, ribs and housings are welded to outer shell after welding to inner shell. A lot of weld grooves should be adjusted for the outer shell weld. The plug weld can allow larger tolerance of weld groove gaps than ordinary butt weld. However, un-welded lengths parallel to outer shell surface remain in the plug weld region. It is necessary to evaluate the allowable un-welded length to apply the plug weld to ITER vacuum vessel fabrication. For the assessment the allowable un-welded lengths have been calculated by crack propagation analyses for the load conditions, conservatively assuming the un-welded region is a crack. The analyses have been carried out for typical inboard straight region and inboard upper curved region with maximum housing stress. The allowable cracks of ribs are estimated to be 8.8mm and 38mm for the rib and the housing, respectively, considering inspection error of 4.4mm. Plug welding for welding between outer shell and ribs/housings could be applicable.
Takeda, Nobukazu; Omori, Junji*; Nakahira, Masataka; Shibanuma, Kiyoshi
Journal of Nuclear Science and Technology, 41(12), p.1280 - 1286, 2004/12
Times Cited Count：3 Percentile：23.52(Nuclear Science & Technology)ITER vacuum vessel (VV) is a safety component confining radioactive materials. An independent VV support structure located at the bottom of VV lower port is proposed as an alternative concept, which is deferent from the current reference, i.e., the VV support is directly connected to the toroidal coil (TF coil). This independent concept has two advantages comparing to the reference one: (1) thermal load becomes lower and (2) the TF coil is categorized as a non-safety component. Stress Analyses have been performed to assess the integrity of the VV support structure. As a result, (1) the maximum displacement of the VV corresponding to the relative displacement between VV and TF coil is found to be 15 mm, much less than the current design value of 100 mm, and (2) the stresses of the whole VV system including VV support are estimated to be less than the allowable ones defined by ASME, respectively. Based on these assessments, the feasibility of the proposed independent VV support has been verified as an alternative VV support.
Takeda, Nobukazu; Omori, Junji*; Nakahira, Masataka; Shibanuma, Kiyoshi
Journal of Nuclear Science and Technology, 41(12), p.1280 - 1286, 2004/12
The vibration experiments of the support structures with flexible plates for the ITER major components such as toroidal field coil and vacuum vessel were performed using small-sized flexible plates aiming to obtain its basic mechanical characteristics such as dependence of the stiffness on the loading angle. The experimental results obtained by the hammering and frequency sweep tests were agreed each other, so that the experimental method is found to be reliable. In addition, the experimental results were compared with the analytical ones in order to estimate an adequate analytical model. As a result, the bolt connection strongly affected on the stiffness of the support structure. After studies of modeling the bolts, it is found that the analytical results modeling the bolts with finite stiffness only in the axial direction and infinite stiffness in the other directions agree well with the experimental ones. Using this model, the stiffness of the support structure for the ITER major components can be calculated precisely in order to estimate the dynamic behaviors.
Mori, Masahiro; Shoji, Teruaki; Araki, Masanori; Saito, Keiji*; Senda, Ikuo; Omori, Junji*; Sato, Shinichi*; Inoue, Takashi; Ono, Isamu*; Kataoka, Takahiro*; et al.
Nihon Genshiryoku Gakkai-Shi, 44(1), p.16 - 89, 2002/01
no abstracts in English
Omori, Junji; Nakahira, Masataka; Takeda, Nobukazu; Kakudate, Satoshi; Shibanuma, Kiyoshi; Sago, Hiromi*; Shimizu, Katsusuke*; Onozuka, Masanori*
no journal, ,
no abstracts in English
Nakahira, Masataka; Takeda, Nobukazu; Kakudate, Satoshi; Omori, Junji; Shibanuma, Kiyoshi; Onozuka, Masanori*; Shimizu, Katsusuke*
no journal, ,
no abstracts in English
Onozuka, Masanori*; Shimizu, Katsusuke*; Usui, Yukinori*; Urata, Kazuhiro*; Namiki, Masao*; Tsujita, Yoshihiro*; Nakahira, Masataka; Takeda, Nobukazu; Kakudate, Satoshi; Omori, Junji; et al.
no journal, ,
no abstracts in English
Nakajima, Hideo; Niimi, Kenichiro; Omori, Junji; Takano, Katsutoshi; Kawano, Katsumi; Tsutsumi, Fumiaki; Hamada, Kazuya; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Nakajima, Hideo; Niimi, Kenichiro; Omori, Junji; Takano, Katsutoshi; Hamada, Kazuya; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Koizumi, Norikiyo; Nakajima, Hideo; Matsui, Kunihiro; Takano, Katsutoshi; Hemmi, Tsutomu; Omori, Junji; Shimizu, Tatsuya; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Oka, Kiyoshi; Seki, Takeshi*; Komori, Yuki
no journal, ,
We developed a new minimally invasive laser device system using a composite-type optical fiberscope. The fiberscope consists of a centrally located 
0.1 mm single fiber for laser treatment and its surrounding about 9,000 (5 
m/piece) fibers for diagnosis. This system enables transmission of an image and 50 W Yb: fiber laser in parallel. By applying our fiberscope to laser treatment in various medical fields, it enables acquisition of an image, laser treatment, blood flow measurement, estimate of distance only in one fiberscope. By using this device for the PDT treatments applied to such as lung and cervical cancers, we expect to spot the irradiated area selectively while looking at a lesion. In this paper, we present a composition of minimally invasive laser therapy device using 1 mm composite-type optical fiberscope, the basics performance experiment result and an application to PDT therapy.
Ogawa, Hiroaki; Kitazawa, Sin-iti; Sugie, Tatsuo; Katsunuma, Atsushi*; Kitazawa, Daisuke*; Omori, Keisuke*; Itami, Kiyoshi
no journal, ,
no abstracts in English
Sugie, Tatsuo; Takeuchi, Masaki; Ishikawa, Masao; Shimada, Takahiko; Katsunuma, Atsushi*; Kitazawa, Daisuke*; Omori, Keisuke*; Itami, Kiyoshi
no journal, ,
no abstracts in English
CuMo
O
Yasui, Yukio*; Fujimura, Akio*; Omori, Kiyoshi*; Igawa, Naoki; Matsukawa, Takeshi*; Yoshida, Yukihiko*; Hoshikawa, Akinori*; Ishigaki, Toru*
no journal, ,
The magnetic structure of CsCuMoO with CuO ribbon chains have been studied by using the neutron powder diffraction. The magnetic reflections were observed below 
= 1.85 K and all of the magnetic reflections overlapped Bragg reflections. Considering that these are 16-Cu
ions in the unit cell, CsCuMoO has the collinear-antiferromagnetic structure.
CuMoO with 
- 
modelYasui, Yukio*; Fujimura, Akio*; Omori, Kiyoshi*; Igawa, Naoki; Matsukawa, Takeshi*; Yoshida, Yukihiko*; Hoshikawa, Akinori*; Ishigaki, Toru*
no journal, ,
The magnetic structure of CsCuMoO has been studied by using the neutron powder diffraction. Cu spins collinearly ordinate along the 
axis and we found that this material has ferromagnetic structure in ribbon chains and antiferromagnetic structure between ribbon chains. Those results indicate that the magnetic structure is strongly inflected with ferromagnetic . In this presentation, the detail of magnetic structure of this material will be discussed.
