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Journal Articles

Effective thermal conductivity measurement of the candidate ceramic breeder pebble beds by the hot wire method

Enoeda, Mikio; Ohara, Yoshihiro; Roux, N.*; Ying, A.*; Pizza, J.*; Malang, J.*

Fusion Technology, 39(No.2 Part.2), p.612 - 616, 2001/03

no abstracts in English

JAEA Reports

Preliminary thermo-mechanical analysis of ITER breeding blanket

*; Kuroda, Toshimasa*; Enoeda, Mikio

JAERI-Tech 98-059, 75 Pages, 1999/01

JAERI-Tech-98-059.pdf:3.12MB

no abstracts in English

JAEA Reports

ITER breeding blanket module design & analysis

Kuroda, Toshimasa*; Enoeda, Mikio; *; *; Sato, Shinichi*; Osaki, Toshio*; Furuya, Kazuyuki; Hatano, Toshihisa; Sato, Satoshi; Takatsu, Hideyuki

JAERI-Tech 98-051, 71 Pages, 1998/11

JAERI-Tech-98-051.pdf:2.74MB

no abstracts in English

Journal Articles

Packing behaviour observed by CT scan for development of pebble bed breeding blanket

*; Sato, Satoshi; Enoeda, Mikio; Takatsu, Hideyuki; *; *; *

Fusion Technology 1998, 2, p.1333 - 1336, 1998/00

no abstracts in English

Journal Articles

Ceramic breeding blanket development for experimental fusion reactor in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Mori, Seiji*; Hashimoto, T.*; Nakahira, Masataka; Furuya, Kazuyuki; Tsunematsu, Toshihide; Seki, Masahiro; Kawamura, Hiroshi; et al.

Fusion Engineering and Design, 27, p.449 - 456, 1995/00

 Times Cited Count:7 Percentile:59.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characteristics of pebble packing and evaluation of sweep gas pressure drop into the in-pile mock-up fusion blanket

Ishitsuka, Etsuo; Nakamichi, Masaru; Kawamura, Hiroshi; Sagawa, Hisashi; *; *; Saito, Minoru

Journal of Nuclear Materials, 212-215, p.881 - 884, 1994/00

 Times Cited Count:2 Percentile:28.05(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Characteristics of pebble packing into in-pile mockup on fusion blanket

Nakamichi, Masaru; Kawamura, Hiroshi; Sagawa, Hisashi; Ishida, Toshikatsu*; Hirata, Shingo*; *

JAERI-M 93-060, 30 Pages, 1993/03

JAERI-M-93-060.pdf:1.18MB

no abstracts in English

Journal Articles

Blanket Materials R & D from engineering aspects of lithium ceramic-beryllium-steel systems in ITER blanket

Yoshida, Hiroshi; Enoeda, Mikio; Nagakura, Masaaki*; *; *

Fusion Technology 1992, Vol.2, p.1547 - 1551, 1993/00

no abstracts in English

Journal Articles

Measurement of effective thermal conductivity of lithium oxide and beryllium sphere packed bed

Enoeda, Mikio; Sato, Satoshi; Kurasawa, Toshimasa; Takatsu, Hideyuki

Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.282 - 285, 1993/00

no abstracts in English

Journal Articles

Packing characteristics of solid breeder for fusion reactor blanket

Nakamichi, Masaru; Kawamura, Hiroshi; Sagawa, Hisashi; Ishida, Toshikatsu*; Hirata, Shingo*; *

FAPIG, 0(132), p.22 - 28, 1992/11

no abstracts in English

JAEA Reports

Test apparatus for ITER blanket pebble packing behavior

Enoeda, Mikio; Yoshida, Hiroshi; Hirata, Shingo*; *

JAERI-M 92-104, 29 Pages, 1992/07

JAERI-M-92-104.pdf:0.77MB

no abstracts in English

JAEA Reports

Japanese contributions to blanket design for ITER

Kuroda, Toshimasa*; Yoshida, Hiroshi; Takatsu, Hideyuki; Seki, Yasushi; Noda, Kenji; Watanabe, H.; Koizumi, Koichi; Nishio, Satoshi; *; *; et al.

JAERI-M 91-133, 191 Pages, 1991/08

JAERI-M-91-133.pdf:5.79MB

no abstracts in English

Oral presentation

Current status and perspectives of thorium nuclear energy systems, 1; Global trend of the developments for thorium nuclear energy systems

Sasa, Toshinobu

no journal, , 

As a part of the activities of the "Research Committee for Thorium Nuclear System" in the Japan Atomic Energy Society, the characteristics, performance and feasibility of the proposed thorium nuclear systems from recently published open documents were surveyed in order to understand the research and development status of the thorium nuclear system around the world. Research has been conducted in the countries using nuclear power in the world such as India, Asia, Europe, and the United States. Pebble fuel or molten salts (thermal and fast neutron systems) are selected as fuel material. Regarding the core thermal output, proposals were selected from several 100 MW for demo reactors and modular reactor to 5 GW for power reactors. For the feasibility point of view, many proposals are still in the concept study phase, but there are a few concepts which aimed at licensing of already approved the domestic environmental impact assessment.

13 (Records 1-13 displayed on this page)
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