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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.
Kato, Atsushi; Hayafune, Hiroki; Kotake, Shoji*
Nuclear Engineering and Design, 280, p.586 - 597, 2014/12
Times Cited Count：4 Percentile：30.92(Nuclear Science & Technology)To improve the economic competitiveness of the Japan Sodium-cooled Fast Reactor (JSFR), several innovative designs have been introduced, e.g. reduction of number of main cooling loop, shorter pipe arrangement by adopting thermally durable material, a compact reactor vessel (RV), integration of a primary pump and an intermediate heat exchanger (IHX). A new approach for construction cost estimation has been introduced to handle innovative technologies, for example, concerning different kinds of material, fabrication processes of equipment etc. As results of cost estimations and the latest conceptual JSFR design, economic goals of Generation IV nuclear energy systems can be achieved by expecting the following cost reduction effects: commodity reduction by adopting innovative design, economy of scale by power generation increase, learning effect etc.
Nishio, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.944 - 948, 2004/11
Low aspect ratio tokamak power reactor with super-conducting toroidal field (TF) coils has been proposed. A center solenoid coil system and an inboard blanket were removed. The key point was how to find the engineering design solution of the TF coil system with the high field and high current density. The coil system with the center post radius of less than 1 m can generate the maximum field of 
20 T. This coil system causes a compact reactor concept, where the plasma major and minor radii of 3.5 m and 1.5 m, respectively and the fusion power of 3 GW.
Shiina, Yasuaki; Sakuragi, Yoichi*; Nishihara, Tetsuo
JAERI-Tech 2003-076, 52 Pages, 2003/09
JAERI-Tech-2003-076.pdf:2.72MB
no abstracts in English
Konishi, Satoshi; Okano, Kunihiko*; Tokimatsu, Koji*; Ito, Keishiro*; Ogawa, Yuichi*
Fusion Engineering and Design, 69(1-4), p.523 - 529, 2003/09
Times Cited Count：4 Percentile：31.64(Nuclear Science & Technology)no abstracts in English
Matsukawa, Makoto; JT-60SC Design Team
Fusion Engineering and Design, 63-64, p.519 - 529, 2002/12
Times Cited Count：15 Percentile：67.86(Nuclear Science & Technology)no abstracts in English
Nishio, Satoshi; Tobita, Kenji; Ushigusa, Kenkichi; Konishi, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1218 - 1230, 2002/11
no abstracts in English
Konishi, Satoshi; Tokimatsu, Koji*
Purazuma, Kaku Yugo Gakkai-Shi, 78(11), p.1192 - 1198, 2002/11
no abstracts in English
Kunitomi, Kazuhiko; Katanishi, Shoji; Shiozawa, Shusaku
Nihon Genshiryoku Gakkai-Shi, 43(11), p.1085 - 1099, 2001/11
no abstracts in English
Muto, Yasushi; Kunitomi, Kazuhiko
Karyoku Genshiryoku Hatsuden, 52(10), p.1279 - 1286, 2001/10
no abstracts in English
Ogawa, Masuro
Enerugi, 34(5), p.81 - 87, 2001/05
no abstracts in English
Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi
JAERI-Tech 2001-018, 88 Pages, 2001/03
JAERI-Tech-2001-018.pdf:5.66MB
no abstracts in English
Sakai, Akihiro
KURRI-KR-56, p.58 - 79, 2001/03
no abstracts in English
Funasaka, Hideyuki; ;
JNC TN1200 2001-002, 209 Pages, 2001/01
JNC-TN1200-2001-002.pdf:7.84MB
no abstracts in English
Tanaka, Toshiyuki; Muto, Yasushi
Karyoku Genshiryoku Hatsuden, 51(10), p.318 - 323, 2000/10
no abstracts in English
; Inagaki, Tatsutoshi*
JNC TY1400 2000-003, 92 Pages, 2000/08
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power company (JAPCO, that is the representative of the electric utilities in Japan) have established a new organization to develop a commercialized fast breeder reactor (FBR) cycle system since July 1, 1999 and feasibility studies (F/S) have been undertaken in order to determine the promising concepts and to define the necessary R&D tasks. In the first two-year phase, a number of candidate concepts will be selected from various options, featuring innovative technologies. In the F/S, the options are evaluated and conceptual designs are examined considering the attainable perspectives for following: (1) ensuring safety, (2) economic competitiveness to future LWRs, (3) efficient utilization of resources, (4) reduction of environmental burden and (5) enhancement of nuclear non-proliferation. The F/S should also guide the necessary R&D to commercialize FBR cycle system.
*
JNC TJ6420 2000-005, 109 Pages, 2000/07
JNC-TJ6420-2000-005.pdf:3.16MB
no abstracts in English
Nishihara, Tetsuo; Hada, Kazuhiko; Nishimura, Kuniyuki*
JAERI-Tech 2000-046, 54 Pages, 2000/07
JAERI-Tech-2000-046.pdf:2.72MB
no abstracts in English
Nibe, Nobuaki; Shimakawa, Yoshio; ; Hayafune, Hiroki; ; ;
JNC TN9400 2000-074, 388 Pages, 2000/06
JNC-TN9400-2000-074.pdf:13.32MB
Large sized sodium-cooled fast breeder reactors of large-size are being studied and have been operated in Japan and many countries. ln this feasibility study, evaluation was made on technical feasibinty for design concepts or 1 loop type and 3 pool types, specially from the viewpoint of improvement of economical competence. The design concepts include the ideas of cost reduction measures such as large-scaled components, reduction of loop number and integration of components on the basic of utilization of sodium characteristics. From the results of the evaluation, it may be possible for all the concepts to attain the economical target of 200 thousands yen per kilowatt, though further confirmation should be made for technical feasibility of those concepts. ln addition, the following items were listed up as further cost-reduction measures. (1)Higher temperature cooling system and steam cycle efficiency (2)Shortening of construction term (3)Reduction of safety systems by using measuring instruments with high performmce (4)Adoption of SG-ACS
; ; ; ;
JNC TN9400 2000-066, 52 Pages, 2000/06
JNC-TN9400-2000-066.pdf:1.82MB
Phase I of feasibility studies on commercialized fast reactor system is being peformed for two years from Japanese Fiscal Year 1999. In this report, results of the study on fluid fuel reactors (especialiy a molten salt fast breeder reactor concept) are described from the viewpoint of technical and economical concerns of the plant system design. ln JFY1999, we have started to investigate the fluid fuel reactors as alternative concepts of sodium cooled FBR systems with MOX fuel, and selected the unique concept of a molten chloride fast, breeder reactor, whose U-Pu fuel cycle can be related to both light water reactors and fast breeder reactors on the basis of present technical data and design experiences. We selected a preliminary composition of molten fuel and conceptual plant design through evaluation of technical and economical issues essential for the molten salt reactors and then compared them with reference design concepts of sodium cooled FBR systems under limited information on the molten chloride fast breeder reactors. The following results were obtained. (1)The molten chloride fast breeder reactors have inherent safety features in the core and plant performances, ad the fluid fuel is quite promising for cost reduction of the fuel fabrication and reprocessing. (2)On the other hand, the inventory of the molten chloride fuel becomes high and thermal conductivity of the coolant is inferior compared to those of sodium cooled FBR systems, then, the size of main components such as lHX's becomes larger and the amount of construction materials is seems to be increased. (3)Furthermore economical vessel and piping materials which contact with the molten chloride salts are required to be developed. From the results, it is concluded that further steps to investigate the molten chloride fast breeder reactor concepts are too early to be conducted.
