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Enoeda, Mikio; Tanigawa, Hisashi; Hirose, Takanori; Nakajima, Motoki; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Kawamura, Yoshinori; Hayashi, Takumi; Yamanishi, Toshihiko; et al.
Fusion Engineering and Design, 89(7-8), p.1131 - 1136, 2014/10
Times Cited Count：21 Percentile：83.89(Nuclear Science & Technology)The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. Regarding the fabrication technology development using F82H, the fabrication of a real scale mockup of the back wall of TBM was completed. Also the assembling of the complete box structure of the TBM mockup and planning of the pressurization testing was studied. The development of advanced breeder and multiplier pebbles for higher chemical stability was performed for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium simulation technology, investigation of the TBM neutronics measurement technology and the evaluation of tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been performed.
Enoeda, Mikio; Tanigawa, Hisashi; Hirose, Takanori; Suzuki, Satoshi; Ochiai, Kentaro; Konno, Chikara; Kawamura, Yoshinori; Yamanishi, Toshihiko; Hoshino, Tsuyoshi; Nakamichi, Masaru; et al.
Fusion Engineering and Design, 87(7-8), p.1363 - 1369, 2012/08
Times Cited Count：36 Percentile：92.04(Nuclear Science & Technology)The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and evaluation toward DEMO blanket, the module fabrication technology development by a candidate structural material, reduced activation martensitic/ferritic steel, F82H, is one of the most critical items from the viewpoint of realization of TBM testing in ITER. Fabrication of a real scale first wall, side walls, a breeder pebble bed box and assembling of the first wall and side walls have succeeded. Recently, the real scale partial mockup of the back wall was fabricated. The fabrication procedure of the back wall, whose thickness is up to 90 mm, was confirmed toward the fabrication of the real scale back wall by F82H. This paper overviews the recent achievements of the development of the WCCB TBM in Japan.
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:48.47MBJAEA-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
. 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.
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：139 Percentile：97.7(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 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).
TiO
pebble bed for a test blanket module in JAEATanigawa, Hisashi; Hoshino, Tsuyoshi; Kawamura, Yoshinori; Nakamichi, Masaru; Ochiai, Kentaro; Akiba, Masato; Ando, Masami; Enoeda, Mikio; Ezato, Koichiro; Hayashi, Kimio; et al.
Nuclear Fusion, 49(5), p.055021_1 - 055021_6, 2009/05
Times Cited Count：23 Percentile：64.37(Physics, Fluids & Plasmas)This paper presents recent achievements of the research activities for the TBM being developed in JAEA, focusing on the pebble bed of the tritium breeder materials and tritium behaviour. For the breeder material, the chemical stability of LiTiO has been improved by LiO additives. In order to analyze the pebble bed behaviour, thermo-mechanical properties of the LiTiO pebble bed has been experimentally obtained. In order to verify nuclear properties of the pebble bed, the activation foil method has been proposed and a preliminary experiment has been conducted. For the tritium behaviour, the chemical densified coating method has been well developed and tritium recovery system has been modified taking account of the design change of the TBM.
Enoeda, Mikio; Tanigawa, Hisashi; Tsuru, Daigo; Hirose, Takanori; Ezato, Koichiro; Yokoyama, Kenji; Dairaku, Masayuki; Seki, Yohji; Suzuki, Satoshi; Mori, Kensuke*; et al.
Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10
; ; *
2000 Western Pacific Geophysics Meeting, 81, 0 Pages, 2000/00
None
Ishido, Akio*; Hasegawa, Ken*; Hanaki, Tatsumi*; Ochiai, Yoji*; Shigeta, Naotaka*; Nagasaki, Yasushi*
JNC TN7400 2005-022, 224 Pages, 1996/04
JNC-TN7400-2005-022.PDF:9.36MB
None
Tsubota, Koji*; Ochiai, Yoji*; Hasegawa, Ken*; Nagasaki, Yasushi*; Yamagishi, Akiko*; Nakano, Katsushi*; Muneto, Masaru*
JNC TN7400 2005-021, 166 Pages, 1995/04
JNC-TN7400-2005-021.PDF:7.06MB
None
Tsubota, Koji*; Ochiai, Yoji*; Hanaki, Tatsumi*; Hasegawa, Ken*; Okita, Masatoshi*; Koide, Kaoru*; Nagasaki, Yasushi*
JNC TN7400 2005-019, 114 Pages, 1993/04
JNC-TN7400-2005-019.PDF:7.46MB
None
Nohara, Tsuyoshi; Seo, Toshihiro; Ochiai, Yoji
PNC TN7410 91-030, 28 Pages, 1991/09
The Tsukiyosi uranium deposit, which is called Tertiary sandstone-type, can be regarded as a potentially useful analogue for geological isolation of radioactive wastes in Japan. In order to understand the geochemical behaviour of U-series nuclides (U-238, U-234, Th-230, Ra-226) under reducing condition, a study on radioactive disequilibrium of rocks was carried out. A total of 185 rock specimens were collected from 6 boreholes and gallery in the uranium mineralized zone, which is situated in paleo-river system, in the direction of east-west. In the system of groundwater flow, the mineralized zone was divided into four: the upper, the middle, the lower, and the lowermost reaches from the west to the east. The initial mineralization were occurred at the period of 10 Ma, and mostly focused on the middle reaches. The following results are obtained by the chemical analysis and alpha and gamma spectorometry. Activity ratios of U-234/U-238 and Th-230/U-234 (for 185 specimens) are mostly within the range of 1.2 and 0.8. In the middle reaches to lower reaches of groudwater flow, activity ratios of Th-230/U-234 are occasionally less than unity. In the middle reaches, the ratios of Th-230/U-234 are less than unity at particularly highly mineralized parts, while the ratios are nearly equal to unity at poorly mineralized parts. Activity ratios of Ra-226/Th-230 (for 185 specimens) were a wide range between 0.6 and 5.1. Combination of the result above-mentioned with chemical properties and decay constants of the nuclides leads to the following conclusions. (1)Uranium and thorium have not migrated significantly during the last one million years. The magnitude of the uranium migration is probably within the range of several ten centimeter. (2)Uranium at the middle to lower reaches has been concentrated during the past several hundred thousand years. It is noteworthy that uranium of severely mineralized parts at the middle reaches have highly redistributed. (3)Radium has been probabl
Honda, Yutaka*; Kashima, Sadamitsu; *; *; *; *; *; *
PNC TN843 79-07, 34 Pages, 1979/07
None
Koizumi, Masumichi; Honda, Yutaka*; Yumoto, Ryozo; *; *; *; Hirasawa, Masayoshi; Yagi, Takao
PNC TN841 79-38, 250 Pages, 1979/06
no abstracts in English
Honda, Yutaka*; Kashima, Sadamitsu; *; *; *; *; *; *
PNC TN841 79-04, 63 Pages, 1979/01
no abstracts in English
Koizumi, Masumichi; Kashima, Sadamitsu; *; *; *; *; *; *
PNC TN841 78-24, 75 Pages, 1978/03
no abstracts in English
Honda, Yutaka*; *; *; Kashima, Sadamitsu
PNC TN841 77-57, 105 Pages, 1977/10
no abstracts in English
May ; 1976)Koizumi, Masumichi; Furuya, Hirotaka; *; Nagai, Shuichiro; Tachibana, Toshimichi; *
PNC TN843 76-04, 40 Pages, 1976/08
None
