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Asakura, Nobuyuki; Shinya, Kichiro*; Tobita, Kenji; Hoshino, Kazuo; Shimizu, Katsuhiro; Uto, Hiroyasu; Someya, Yoji; Nakamura, Makoto; Ono, Noriyasu*; Kobayashi, Masahiro*; et al.
Fusion Science and Technology, 63(1T), p.70 - 75, 2013/05
no abstracts in English
Sato, Satoshi; Nishitani, Takeo; Konno, Chikara
no journal, ,
Lithium in a breeding blanket is burned up through neutron nuclear reactions in fusion DEMO reactors. Effects of decrease of solid breeder materials due to lithium burn-up on tritium breeding ratio (TBR) are not systematically calculated in the past. For the SlimCS blanket design, TBR is calculated taking into account the lithium burn-ups by one dimensional Sn radiation transport calculation code ANISN in this study. The 
Li burn-ups are 8 - 79% after 10-year operation. TBR due to Li decreases to 40 % of the initial one in some layer, while it increases in some layers. The TBR integrated over all the blanket decreases to around 96% of the initial one. The study makes it clear that the reduction of the TBR due to the lithium burn-up is not so large.
Ozawa, Kazumi; Nozawa, Takashi; Tanigawa, Hiroyasu
no journal, ,
Tensile and interfacial properties of unidirectional SiC/SiC model composites reinforced with Hi-Nicalon Type-S fibers with innermost pyrolytic carbon (PyC) layer thickness of 
240 and 1150 nm (TypeS-240 and TypeS-1150, respectively) were evaluated by unloading/reloading cyclic tensile tests and single fiber push-out tests. Effective fiber bundle strength in the TypeS-240 and -1150 composites were 79-104% and 70-85%, compared with the original fiber bundle strength. According to the analytic results using hysteresis loops of tensile curves, interfacial sliding stress of the TypeS-1150 estimated to be about 0.7 times as large as the TypeS-240. This tendency was also confirmed by the single fiber push-out tests. These composites showed quasi-ductility, but it is considered that the composite with the thicker interphase could not achieve its fiber bundle strength, probably due to the lower interfacial sliding stress.
Kizu, Kaname; Murakami, Haruyuki; Tsuchiya, Katsuhiko; Kashiwa, Yoshitoshi; Ichige, Toshikatsu; Yoshida, Kiyoshi
no journal, ,
The novel cooling method of central solenoid (CS) was studied to extend the inner space and to shorten the total height of CS for JT-60SA. The cooling pipes and insulation breaks become 0 and 50% of initial design, respectively. The height becomes 2.3 m shorter. The thermo hydraulic analysis showed the sufficient temperature margin 
1K. The superconductor manufacturing factory was constructed at Naka site of JAEA in 2008. The manufacturing of CS conductors was started in 2011. One 238 m and six 466 m conductors were produced.
BeO
for high-functional tritium breederHoshino, Tsuyoshi; Natori, Yuri*; Sakka, Tomoko*; Kato, Kenichi*; Oikawa, Fumiaki; Nakamura, Mutsumi*; Tatenuma, Katsuyoshi*
no journal, ,
no abstracts in English
Nakamichi, Masaru; Kim, Jae-Hwan
no journal, ,
no abstracts in English
Miyamoto, Seiji; Isayama, Akihiko; Sugihara, Masayoshi*; Kusama, Yoshinori
no journal, ,
Accurate modeling of VDEs (Vertical Displacement Events) and plasma disruptions is crucial for estimating disruption-induced forces and heat loads. So far the DINA code has been devoted to the ITER disruption analysis. However, it is important to validate the code results with other codes and experiments. The TSC code is one of the most widely used codes in flux evolution simulation as well as the DINA code. TSC and DINA take very different approach in calculating flux evolution and, therefore, it is worth benchmarking DINA against TSC for revealing the model difference and its effect on the accuracy of simulations. In the past, such benchmark activity was conducted but significant differences could not be diminished due to a large number of model differences. In this study, resistivity of the plasma, time constants of blanket modules and initial plasma equilibrium in the both codes are carefully adjusted each other. The result shows an excellent match in current quench behavior and VDE motion. This observation confirms the reliability of the DINA analysis of ITER disruption. Finally halo current model used in DINA and TSC is benchmarked against experimental data from ASDEX-U. Some needs of model extension, especially necessity of sheath constraint, are discussed.
Kusama, Yoshinori
no journal, ,
no abstracts in English
Ishikawa, Masao; Kondoh, Takashi; Kusama, Yoshinori
no journal, ,
Fusion power and its time evolution on ITER will be evaluated in terms of the total neutron emission rate as measured with neutron flux monitors. Since a level of accuracy within 10% is required for evaluation of the fusion power in ITER, the relation between the neutron monitor outputs and the total neutron emission rate must exceed this accuracy level in an absolute sense. In ITER, the absolute calibration factors of the neutron flux monitors will be obtained by means of a neutron 
calibration procedure. The basic strategy of the calibration has been studied. In this talk, results of neutronic analysis applied to calibration of in-vessel neutron flux monitor, Microfission chambers (MFCs) are presented
Takeuchi, Masaki; Sugie, Tatsuo; Ogawa, Hiroaki; Kusama, Yoshinori; Ebisawa, Katsuyuki*; Wakabayashi, Kunio*; Nariai, Kyoji*; Tanimoto, Aki*; Kiyohara, Motosuke*
no journal, ,
no abstracts in English
Imazawa, Ryota; Ono, Takehiro; Kawano, Yasunori; Kusama, Yoshinori
no journal, ,
no abstracts in English
Kawashima, Hisato; Kubo, Hirotaka; Arai, Takashi; Masaki, Kei; Yagyu, Junichi; Hasegawa, Koichi; Shibanuma, Kiyoshi
no journal, ,
The design study of JT-60SA has been carried out efficiently using the CAD system. Main components such as the vacuum vessel (VV) were distinguished for 24 items and CAD designers began with the design of parts and assembly on every item. Basic design is almost completed except the manufactured apparatuses such as VV. All components are being integrated as the large-assembly to study the interference and accessibility among those components. This large-assembly model consists of 10,000 parts and 4 GB volume at present, corresponding the largest scale structure in this field. Special difficulties are produced as that the existing computer (PC) cannot cover enough and CAD data of each component must be managed unified. Therefore, it is carried out to optimize the PC, to reduce the volume using the favorable function of CAD, and to introduce the data management system. Thus, handling of JT-60SA large-assembly model, which becomes a large scale more, is in progress.
Kim, Jae-Hwan; Nakamichi, Masaru
no journal, ,
no abstracts in English
Matsui, Kunihiro; Hemmi, Tsutomu; Iguchi, Masahide; Kajitani, Hideki; Chida, Yutaka; Koizumi, Norikiyo; Nakajima, Hideo
no journal, ,
no abstracts in English
Akiba, Masato; Enoeda, Mikio
no journal, ,
no abstracts in English
Suzuki, Satoshi; Ezato, Koichiro; Seki, Yohji; Nishi, Hiroshi; Hirose, Takanori; Mori, Kensuke; Enoeda, Mikio
no journal, ,
no abstracts in English
Koizumi, Norikiyo; Nunoya, Yoshihiko; Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi
no journal, ,
no abstracts in English
Miyata, Yoshiaki; Suzuki, Takahiro; Fujita, Takaaki; Ide, Shunsuke; Urano, Hajime
no journal, ,
no abstracts in English
Shibata, Yoshihide; Ide, Shunsuke; Fujita, Takaaki; Isayama, Akihiko; Watanabe, Kiyomasa*; Oyama, Naoyuki; Kurihara, Kenichi; Kawano, Yasunori; Sugihara, Masayoshi*
no journal, ,
no abstracts in English
Tanigawa, Hisashi
no journal, ,
Blanket is an in-vessel component that has three functions of heat removal for power generation, tritium breeding and neutron shielding. We call the blanket in ITER as the shielding blanket, because its function is limited to only the neutron shielding. The blanket is one of the important equipments those functions will be very different between ITER and DEMO reactor. In order to study characteristics of the fusion power reactor related to safety aspect, safety studies previously done for ITER is referred focusing on the difference from the DEMO reactor. Among different accidents that have a potential to damage the vacuum vessel, LOCA is very important because decay heat will be much higher in the DEMO reactor than in ITER.
