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Journal Articles

Perspective of negative triangularity tokamak as fusion energy system

Kikuchi, Mitsuru; Medvedev, S.*; Takizuka, Tomonori*; Fasoli, A.*; Wu, Y.*; Diamond, P. H.*; Duan, X.*; Kishimoto, Yasuaki*; Hanada, Kazuaki*; 41 of others*

Europhysics Conference Abstracts (Internet), 39E, p.P4.179_1 - P4.179_4, 2015/06

Power and particle control in fusion reactor is quite a challenge and we have studied the negative triangularity tokamak (NTT) as an innovative concept to reduce the transient ELM heat load and the quasi steady-state heat load. A double-null NTT is stable to ideal MHD modes for a reactor relevant bN $$>$$ 3 while it is a magnetic hill configuration. In this paper, we report the configuration study of single-null NTT and its ideal MHD stability.

Journal Articles

Actively convected liquid metal divertor

Shimada, Michiya; Hirooka, Yoshihiko*

Nuclear Fusion, 54(12), p.122002_1 - 122002_7, 2014/12

 Times Cited Count:23 Percentile:16.87(Physics, Fluids & Plasmas)

Tungsten is considered to be the most promising material for divertor in a fusion reactor. Tungsten divertor can withstand the heat loads of ITER, but the heat loads of DEMO divertor is a challenge. Pulsive heat loads as those associated with disruption could melt tungsten targets. The surface would not be flat after subsequent resolidification, which would significantly deteriorate its heat handling capability. Furthermore, DBTT of tungsten is rather high: $$sim$$ 400$$^{circ}$$C, which would become even higher after neutron irradiation, possibly resulting in cracks in tungsten. Our proposal is to use liquid metal for the divertor target material and actively circulate it with $$j$$ $$times$$ $$B$$ force. A simplified analysis of mhd equation in a cylindrical geometry suggests that the engineering requirement is modest. This analysis suggests that this new divertor concept merits further investigation.

Journal Articles

Vapor species evolved from Li$$_{2}$$TiO$$_{3}$$ heated at high temperature under various conditions

Hoshino, Tsuyoshi; Yasumoto, Masaru*; Tsuchiya, Kunihiko; Hayashi, Kimio; Nishimura, Hidetoshi*; Suzuki, Akihiro*; Terai, Takayuki*

Fusion Engineering and Design, 81(1-7), p.555 - 559, 2006/02

 Times Cited Count:13 Percentile:29.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of contact strength of Li$$_{2}$$TiO$$_{3}$$ pebbles with different diameters

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Tanaka, Satoru*

Fusion Engineering and Design, 81(8-14), p.1065 - 1069, 2006/02

 Times Cited Count:9 Percentile:42.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experiment and analyses for 14 MeV neutron streaming through a dogleg duct

Yamauchi, Michinori*; Ochiai, Kentaro; Morimoto, Yuichi*; Wada, Masayuki*; Sato, Satoshi; Nishitani, Takeo

Radiation Protection Dosimetry, 116(1-4), p.542 - 546, 2005/12

 Times Cited Count:3 Percentile:73.52(Environmental Sciences)

no abstracts in English

Journal Articles

Confinement of alpha particles in a low-aspect-ratio tokamak reactor

Tani, Keiji; Tobita, Kenji; Iio, Shunji*; Tsutsui, Hiroaki*; Nishio, Satoshi; Aoki, Takayuki*

Denki Gakkai Rombunshi, A, 125(11), p.938 - 942, 2005/11

Studies on the loss of fusion produced alpha particles enhanced by toroidal field (TF) ripple in a low-aspect-ratio tokamak reactor (VECTOR) have been made by using an orbit-following Monte-Carlo code. The ripple loss is strongly reduced as the aspect ratio becomes low. Consequently, alpha particles are well confined in VECTOR. Thanks to the good confinement of alphas in a low-aspect-ratio system, the number of TF coils can be reduced to about 6, one half of the original VECTOR, by installing cooling systems near the outer edge of plasma and making allowances for about 30% increase in the bore diameter of TF coils.

Journal Articles

Effects of gelation and sintering conditions on granulation of Li$$_{2}$$TiO$$_{3}$$ pebbles from Li-Ti complex solution

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Casadio, S.*; Alvani, C.*

Fusion Engineering and Design, 75-79, p.877 - 880, 2005/11

 Times Cited Count:22 Percentile:16.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Behavior on Li$$_{2}$$TiO$$_{3}$$ under varied surface condition

Olivares, R.*; Oda, Takuji*; Oya, Yasuhisa*; Tanaka, Satoru*; Tsuchiya, Kunihiko

Fusion Engineering and Design, 75-79, p.765 - 768, 2005/11

 Times Cited Count:8 Percentile:47.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Non-stoichiometry of Li$$_{2}$$TiO$$_{3}$$ under hydrogen atmosphere condition

Hoshino, Tsuyoshi; Tsuchiya, Kunihiko; Hayashi, Kimio; Terai, Takayuki*; Tanaka, Satoru*; Takahashi, Yoichi*

Fusion Engineering and Design, 75-79, p.939 - 943, 2005/11

 Times Cited Count:9 Percentile:43.23(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Control of particle size and density of Li$$_{2}$$TiO$$_{3}$$ pebbles fabricated by indirect wet processes

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Takayama, Tomoo*; Kato, Shigeru*

Journal of Nuclear Materials, 345(2-3), p.239 - 244, 2005/10

 Times Cited Count:36 Percentile:7.73(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Intelligible seminar on fusion reactors, 8; Fuel cycling system for tritium recovery

Fukada, Satoshi*; Hayashi, Takumi

Nippon Genshiryoku Gakkai-Shi, 47(9), p.623 - 629, 2005/09

no abstracts in English

Journal Articles

Intelligible seminar on fusion reactors, 7; Optimum materials for the realization of fusion reactor

Hasegawa, Akira*; Tsuchiya, Kunihiko; Ishitsuka, Etsuo

Nippon Genshiryoku Gakkai-Shi, 47(8), p.536 - 544, 2005/08

no abstracts in English

JAEA Reports

Li depletion effects on Li$$_{2}$$TiO$$_{3}$$ reaction with H$$_{2}$$ in thermo-chemical environment relevant to breeding blanket for fusion power plants

Alvani, C.*; Casadio, S.*; Contini, V.*; Giorgi, R.*; Mancini, M. R.*; Tsuchiya, Kunihiko; Kawamura, Hiroshi

JAERI-Review 2005-024, 28 Pages, 2005/07

JAERI-Review-2005-024.pdf:5.73MB

no abstracts in English

Journal Articles

Local bonding states of ion-irradiated graphite characterized by photon-stimulated desorption (PSD) spectroscopy

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:81.33(Spectroscopy)

no abstracts in English

Journal Articles

Estimation of radioactivities in the IFMIF liquid lithium loop due to the erosion and corrosion of target back-wall

Yamauchi, Michinori*; Takemura, Morio*; Nakamura, Hiroo; Fischer, U.*; Ida, Mizuho*; Mori, Seiji*; Sato, Satoshi; Nishitani, Takeo; Simakov, S. P.*; Sugimoto, Masayoshi

Fusion Science and Technology, 47(4), p.1008 - 1011, 2005/05

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Low temperature tritium release experiment from lithium titanete breeder material

Tsuchiya, Kunihiko; Kawamura, Hiroshi; Nakamichi, Masaru*; Sagawa, Hisashi

JAERI-Tech 2005-013, 56 Pages, 2005/03

JAERI-Tech-2005-013.pdf:6.4MB

no abstracts in English

Journal Articles

Intelligible Seminar on fusion reactors, 4; Plasma control and diagnostics system

Kurihara, Kenichi

Nippon Genshiryoku Gakkai-Shi, 47(3), p.200 - 207, 2005/03

no abstracts in English

Journal Articles

Optimization study on the normal conducting center post for the low aspect ratio tokamak reactor

Song, Y.*; Nishio, Satoshi

Fusion Engineering and Design, 72(4), p.345 - 362, 2005/01

 Times Cited Count:6 Percentile:56.45(Nuclear Science & Technology)

This paper presents detailed optimization results and design windows for the engineering design of normal conducting (NC) center post based on the analysis of thermal-hydraulic, static stress and critical buckling. At the same time a method to reduce the stress in the center post have been proposed, which can be applied to enhance the possibility of normal conducting center post in the future power plants. When the method of improvement for reducing the stress is applied in the system of the center post, the maximum magnet field can be improved from 8.6T to 15T.

Journal Articles

Introduction of plasma characteristics for fusion reactor design

Kamada, Yutaka

Nippon Genshiryoku Gakkai-Shi, 47(1), p.45 - 52, 2005/01

no abstracts in English

Journal Articles

Extra radiation hardening and microstructural evolution in F82H by high-dose dual ion irradiation

Ando, Masami; Wakai, Eiichi; Sawai, Tomotsugu; Matsukawa, Shingo; Naito, Akira*; Jitsukawa, Shiro; Oka, Keiichiro*; Tanaka, Teruyuki*; Onuki, Somei*

JAERI-Review 2004-025, TIARA Annual Report 2003, p.159 - 161, 2004/11

The objectives of this study are to evaluate radiation hardening on ion-irradiated F82H up to 100 dpa and to examine the extra component of radiation hardening due to implanted helium atoms (up to $$sim$$3000 appmHe) in F82H under ratio of 0, 10, 100 appmHe/dpa.The ion-beam irradiation experiment was carried out at the TIARA facility of JAERI. Specimens were irradiated at 633 K by 10.5 MeV Fe ions with/without 1.05 MeV He ions. Micro-indentation tests were performed at loads to penetrate about 0.40 mm in the irradiated specimens using an UMIS-2000. The results are summarized as follows:1) As a result of the single irradiated F82H, the micro-hardness tended to increase about 30 dpa. 2) The extra radiation hardening was obviously caused by co-implanted helium atoms more than 1000 appm in F82H irradiated at 633 K. 3) In the dual-beam (100 appmHe/dpa) irradiated microstructure, nano-voids and fine defects were observed. It is suggested that the formation of nano-voids causes the extra radiation hardening by helium co-implantation.

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