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Journal Articles

Neutron shielding and blanket neutronics design

Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.952 - 954, 2004/11

Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.

Journal Articles

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.

Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12

 Times Cited Count:91 Percentile:5.84(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Preliminary neutronic estimation for demo blanket with beryllide

Yamada, Hirokazu*; Nagao, Yoshiharu; Kawamura, Hiroshi; Nakao, Makoto*; Uchida, Munenori*; Ito, Haruhiko

Fusion Engineering and Design, 69(1-4), p.269 - 273, 2003/09

 Times Cited Count:12 Percentile:34.53

no abstracts in English

Journal Articles

Core and system design of Reduced-Moderation Water Reactor with passive safety features

Iwamura, Takamichi; Okubo, Tsutomu; Yonomoto, Taisuke; Takeda, Renzo*; Moriya, Kumiaki*; Kanno, Minoru*

Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 8 Pages, 2002/00

Research and developments of reduced-moderation water reactor (RMWR) have been performed. The RMWR can attain the favorable characteristics such as high burn-up, long operation cycle, multiple recycling of plutonium and effective utilization of uranium resources, based on the matured LWR technologies. MOX fuel assemblies in the tight-lattice fuel rod arrangement are used to reduce the moderation of neutron, and hence, to increase the conversion ratio. The conceptual design has been accomplished for the small 330MWe RMWR core with the discharge burn-up of 60GWd/t and the operation cycle of 24 months, under the natural circulation cooling of the core. A breeding ratio of 1.01 and the negative void reactivity coefficient are simultaneously realized in the design. In the plant system design, the passive safety features are intended to be utilized mainly to improve the economy. At present, a hybrid one under the combination of the passive and the active components, and a fully passive one are proposed. The former has been evaluated to reduce the cost for the reactor components.

Journal Articles

Nuclear and thermal analyses of supercritical-water-cooled solid breeder blanket for fusion DEMO reactor

Yanagi, Yoshihiko*; Sato, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Kikuchi, Shigeto*; Kuroda, Toshimasa*; Kosaku, Yasuo; Ohara, Yoshihiro

Journal of Nuclear Science and Technology, 38(11), p.1014 - 1018, 2001/11

 Times Cited Count:21 Percentile:16.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Possible scenario to start up DT fusion plant without initial loading of tritium

Konishi, Satoshi; Asaoka, Yoshiyuki*; Hiwatari, Ryoji*; Okano, Kunihiko*

Purazuma, Kaku Yugo Gakkai-Shi, 76(12), p.1309 - 1312, 2000/12

no abstracts in English

JAEA Reports

A Design study on a large FBR plant enhancing passive safety

Hayashi, Hideyuki; ;

PNC-TN9410 96-062, 186 Pages, 1996/02

PNC-TN9410-96-062.pdf:5.83MB

A conceptual design study on a 1300MWe large FBR plant was performed with focusing on enhancing passive safety and capital cost reduction. Spectrum-adjusted mixed nitride fueled core in which zirconium hydride was added, was applied to enlarge Doppler reactivity coefficient. Breeding ratio of 1.2 was obtained only with one layer of radial blanket subassemblies by optimizing the content of the zirconium hydride. The optimization also lightened the burden to the reactor structure through the reduction of the core diameter. Reactor passive shutdown were performed in the ATWS events of ULOF and ULOHS, and UTOP caused by one control rod full runout was endurable under the criterion of the prevention of coolant boiling. The safety feature can be called as inherent safety, because the feature comes only from the reactivity characteristics of the core. The integrities of the reactor structures which characterize head-access loop type reactor were evaluated on the transient thermal stress at the loss of flow accident and on seismic strain. Vertical strain of core support plate at loss of flow condition was also evaluated on the passive shutdown at ULOF. The capital cost of the large FBR plant was estimated 1.3 to 1.4 times as high as that of the same scale LWR based on the weight of major components.

JAEA Reports

Test program development for ITER blanket design

Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; Nakahira, Masataka; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 95-021, 25 Pages, 1995/03

JAERI-Tech-95-021.pdf:0.97MB

no abstracts in English

Journal Articles

A Design study for inherent safety core, aseismicity and heat transport system in lead-cooled nitride-fuel fast reactor

Takano, Hideki; ; ; *; *; *

Proc. of ARS94 Int. Topical Meeting on Advanced Reactors Safety,Vol. 1, 0, p.549 - 556, 1994/00

no abstracts in English

Journal Articles

A High-breeding fast reactor with fission product gas purge/tube-in shell metallic fuel assemblies

; ; Takano, Hideki; *; *

Nuclear Technology, 93, p.305 - 329, 1991/03

 Times Cited Count:9 Percentile:29.1(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of Increasing Tritium Breeding Ratios of JXFR and INTOR-J Blanket

;

JAERI-M 8896, 11 Pages, 1980/06

JAERI-M-8896.pdf:0.56MB

no abstracts in English

JAEA Reports

Breeding Potential of Carbide,Nitride and Oxide Fueled LMFBR and GCFR

JAERI-M 7374, 55 Pages, 1977/11

JAERI-M-7374.pdf:1.84MB

no abstracts in English

JAEA Reports

The Strategy for Development of Advanced Fuel for LMFBR

JAERI-M 6851, 59 Pages, 1976/12

JAERI-M-6851.pdf:2.05MB

no abstracts in English

JAEA Reports

JAEA Reports

Neutronics of JAERI Experimental Fusion Reactors Blanket

; ; *

JAERI-M 6460, 21 Pages, 1976/03

JAERI-M-6460.pdf:0.66MB

no abstracts in English

JAEA Reports

Neutronic Calculation on Fussion Reactor Blanket by Sn-Approximation

*; ;

JAERI-M 6072, 28 Pages, 1975/03

JAERI-M-6072.pdf:0.77MB

no abstracts in English

22 (Records 1-20 displayed on this page)