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Ogawa, Masuro
Nuclear Engineering and Design, 308, p.133 - 141, 2016/11
Times Cited Count：2 Percentile：19.71(Nuclear Science & Technology)A new basic concept on safety; Not causing any serious catastrophe by any means and a new basic concept on radioactive waste; Not returning any waste that possibly affects the environment are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima in 2011. In the present study, physical phenomena are used to continue confining, rather than confine. To continue confining is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB. The New HTGR is proposed based on the new basic concepts. It is indicated that the New HTGR can response to social requirements for safety and environmental conservability against radioactive wastes, industrial requirements for economy, uranium resource sustainability and so on, and national requirements for non-proliferation and environmental protection against carbon dioxide.
McCracken, G.*; Stott, P.*; Iiyoshi, Atsuo*; Muraoka, Katsunori*; Nakai, Sadao*; Shimada, Michiya
Kaku Yugo; Uchu No Enerugi O Watashitachi No Te Ni, 326 Pages, 2015/00
Fusion; The Energy of the Universe, 2e is an essential reference providing basic principles of fusion energy from its history to the issues and realities progressing from the present day energy crisis. The book provides detailed developments and applications for researchers entering the field of fusion energy research. This second edition includes the latest results from the National Ignition Facility at the Lawrence Radiation Laboratory at Livermore, CA, and the progress on the International Thermonuclear Experimental Reactor (ITER) tokamak programme at Caderache, France.
Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.
Nuclear Fusion, 45(12), p.1618 - 1627, 2005/12
Times Cited Count：18 Percentile：51.39(Physics, Fluids & Plasmas)no abstracts in English
Polevoi, A. R.*; Shimada, Michiya; Sugihara, Masayoshi; Igitkhanov, Y. L.*; Mukhovatov, V.*; Kukushkin, A. S.*; Medvedev, S. Y.*; Zvonkov, A. V.*; Ivanov, A. A.*
Nuclear Fusion, 45(11), p.1451 - 1456, 2005/11
Times Cited Count：33 Percentile：70.37(Physics, Fluids & Plasmas)Requirements for pellet injection parameters for plasma fuelling are assessed for ITER scenarios with enhanced particle confinement. A pellet injection throughput of 100 Pam
/s would be sufficient. The assessment is based on the integrated transport simulations including models of pedestal transport, reduction of helium transport and boundary conditions compatible with SOL/divertor simulations. The requirements for pellet injection for the inductive H-mode scenario (HH98(y,2) = 1) are reconsidered taking account of a possible reduction of the particle loss obtained in some experiments at low collisionalities. The assessment of fuelling requirements is carried out for the hybrid and steady state scenarios with enhanced confinement with HH98(y,2) 
1. A robustness of plasma performance to the variation of particle transport is demonstrated. A new type of steady state (SS) scenario is considered with neutral beam current drive (NBCD) and electron cyclotron current drive (ECCD) instead of lower hybrid current drive (LHCD).
Sakamoto, Yoshiteru; Toi, Kazuo*; Fukuda, Takeshi*; Fukuyama, Atsushi*; Fujita, Takaaki; Ogawa, Yuichi*; Takizuka, Tomonori; Takenaga, Hidenobu; Yagi, Masatoshi*; Yamada, Hiroshi*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 81(8), p.626 - 627, 2005/08
no abstracts in English
Iwai, Yasunori; Hayashi, Takumi; Kobayashi, Kazuhiro; Nishi, Masataka
Fusion Science and Technology, 48(1), p.460 - 463, 2005/07
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)A code has been developed to investigate tritium behavior in a ventilated room at its accidental release. Purpose of present study is to; (1) investigate the effect of atmospheric exchange number on confinement at initial stage of tritium release; (2) investigate the effect of atmospheric exchange number on time necessary for release detection; (3) investigate the suitable location of exhaust ducts and monitors. Essential points of discussion are as follows: (1) Atmospheric exchange number is less influential in confinement. (2) Time until a monitor detects release depends on exchange number but it is within a few minutes in any case. Installation of a monitor in each duct placed uniformly in a room is effective for the prompt detection. (3) After closing the emergency isolation valve, a few hours are needed until the tritium concentration in a room reaches uniform. Released tritium forms plume and it migrates in a room by the eddy flow at its initial stage, so it is important not to discharge plume directly. Hence, it is effective to locate exhaust ducts with some distance from the wall.
Urano, Hajime; Kamada, Yutaka; Takizuka, Tomonori; Suttrop, W.*; Horton, L.*; Lang, P.*; Kubo, Hirotaka; Oyama, Naoyuki; Takenaga, Hidenobu; Asakura, Nobuyuki
Purazuma, Kaku Yugo Gakkai-Shi, 81(4), p.280 - 287, 2005/04
Role of the pedestal structure in ELMy H-mode plasmas for the core energy confinement and for the ELM energy losses have been investigated in JT-60U and ASDEX Upgrade. The confinement degradation seen at higher densities is attributed to the reduction of the pedestal temperature limited by the ELM activities and the stiffness of the temperature profiles. In high triangularity or impurity seeded H-modes, in which higher energy confinement is generally achieved, higher pedestal temperature is obtained by the improvement of the edge MHD stability or the density profile peaking, respectively. The upper bound of the ELM energy loss is characterised by the pedestal energy. The energy transport in between ELMs enhanced with increasing the pedestal collisionality reduces the ELM loss power fraction. It is also shown in ASDEX Upgrade that the continuous pellet injection is valid for the integrated performance of smaller ELM losses and favourable core confinement.
Yoshikawa, Kiyoshi*; Takiyama, Ken*; Onishi, Masami*; Yamamoto, Yasushi*; Nagasaki, Kazunobu*; Masuda, Kai*; Toku, Hisayuki*; Horiike, Hiroshi*
JAERI-Tech 2005-006, 116 Pages, 2005/03
JAERI-Tech-2005-006.pdf:24.79MB
no abstracts in English
Urano, Hajime
JAERI-Research 2004-027, 131 Pages, 2005/02
JAERI-Research-2004-027.pdf:5.69MB
no abstracts in English
Kamada, Yutaka
Nihon Genshiryoku Gakkai-Shi, 47(1), p.45 - 52, 2005/01
no abstracts in English
Asakura, Nobuyuki
Plasma Physics and Controlled Fusion, 46(12B), p.B335 - B347, 2004/12
Times Cited Count：18 Percentile：51.27(Physics, Fluids & Plasmas)Particle control of the main plasma density and exhaust of impurities ions have been demonstrated using the divertor pumping under saturated divertor condition. In JT-60U, ELMy H-mode operation was recently extended to 30s (with NB heating of 8-14 MW). Total number of injected particles reached (1-4)x1023 to maintain high densities. During the long pulse ELMy H-mode of JT-60U, gas puff rate was decreased from 15 to 3Pam3/s, while pumping rate was relatively constant of ~10 Pam3/s. Thus, the divertor plate was mostly saturated. It was found that 40-50% of the injected D was retained, which are comparable to Tore-Supra long pulse and JET high density ELMy H-mode pulse. Particle balance for long pulse and/or high density plasmas are discussed. Carbon flux generated by the chemical process was increased due to increase in the target temperature. Carbon generation and carbon ion emission were gradually increased in the outer leg of the divertor and the X-point. Shielding effect of the divertor was sustained and increment of the radiation power fraction was small in 30s.
Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.
Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11
no abstracts in English
Sakamoto, Yoshiteru; Toi, Kazuo*; Fukuda, Takeshi*; Fukuyama, Atsushi*; Fujita, Takaaki; Ogawa, Yuichi*; Takizuka, Tomonori; Miura, Yukitoshi; Yagi, Masatoshi*; Yamada, Hiroshi*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 80(8), P. 678, 2004/08
no abstracts in English
Tobita, Kenji; Ozeki, Takahisa; Nakamura, Yukiharu
Plasma Physics and Controlled Fusion, 46(7), p.S95 - S105, 2004/07
Times Cited Count：10 Percentile：32.04(Physics, Fluids & Plasmas)no abstracts in English
Yamada, Hirokazu*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Ishitsuka, Etsuo; Uchida, Munenori*; Akutsu, Yoichi; Motoki, Ryozo; Watanabe, Wataru; Hirata, Shogo*
JAERI-Tech 2004-036, 138 Pages, 2004/03
JAERI-Tech-2004-036.pdf:4.07MB
This document shows the model case concerned with the utilization of constructed facility for the construction of post irradiation examination facility for fusion blanket. In this report, the radioisotope application and development laboratory is considered as constructed facility for post irradiation examination facility and we planned to improve the radioisotope application and development laboratory to the facility of post irradiation examination for fusion material to reduce the construction fee for this facility and promotion of efficiency by concentration of any equipment for fusion material research.
Takenaga, Hidenobu; Oyama, Naoyuki; Fujita, Takaaki; Yamada, Hiroshi*; Nishimura, Kiyohiko*; Tanaka, Kenji*; Sakamoto, Ryuichi*
Annual Report of National Institute for Fusion Science; April 2003 - March 2004, P. 12, 2003/10
no abstracts in English
Mukhovatov, V.*; Shimomura, Yasuo; Polevoi, A. R.*; Shimada, Michiya; Sugihara, Masayoshi; Bateman, G.*; Cordey, J. G.*; Kardaun, O. J. F.*; Pereverzev, G. V.*; Voitsekhovich, I.*; et al.
Nuclear Fusion, 43(9), p.942 - 948, 2003/09
Times Cited Count：43 Percentile：76.69(Physics, Fluids & Plasmas)The values of Q = (fusion power)/(auxiliary heating power) predicted for ITER by three different methods are compared. The first method utilises an empirical confinement time scaling and prescribed radial profiles of transport coefficients, the second approach extrapolates from especially designed ITER similarity experiments, and the third approach is based on partly theory-based transport models. The energy confinement time given by the ITERH-98(y,2) scaling for an inductive scenario with plasma current of 15 MA and plasma density 15% below the Greenwald density is 3.7 s with one estimated technical standard deviation of 14%. This translates in the first approach into an interval for Q of [6-15] at the auxiliary heating power Paux = 40 MW and [6-30] at the minimum heating power satisfying a good confinement ELMy H-mode. Predictions of similarity experiments from JET and of theory-based transport models overlap with the prediction using the empirical confinement-time scaling within its estimated margin of uncertainty.
Takizuka, Tomonori; Ogawa, Yuichi*; Miura, Yukitoshi; Yagi, Masatoshi*; Fujita, Takaaki; Toi, Kazuo*; Fukuda, Takeshi*; Fukuyama, Atsushi*; Ida, Katsumi*; *; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 79(6), p.628 - 629, 2003/06
no abstracts in English
Ninomiya, Hiromasa
Nihon Genshiryoku Gakkai-Shi, 45(4), p.243 - 248, 2003/04
no abstracts in English
Department of Fusion Plasma Research Tokamak Program Division
JAERI-Review 2003-012, 41 Pages, 2003/03
JAERI-Review-2003-012.pdf:3.97MB
This report summarizes the contributed papers of the 19th IAEA Fusion Energy Conference held at Lyon, France, from October 14th to 19th, 2002.
