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JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

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:22 Percentile:16.59(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical analysis model for thermal conductivities of packed beds with high solid-to-gas conductivity ratio

Kikuchi, Shigeto*

International Journal of Heat and Mass Transfer, 44(6), p.1213 - 1221, 2001/03

 Times Cited Count:12 Percentile:46.47(Thermodynamics)

no abstracts in English

Journal Articles

Basic characteristics of heat transfer in pebble beds with high solid to gas conductivity ratio; A New numerical analysis model for effective thermal conductivity in near wall and bulk region

Kikuchi, Shigeto*; Enoeda, Mikio; Ohara, Yoshihiro

Proceedings of the 9th International Workshop on Ceramic Breeder Blanket Interactions (CBBI-9), p.191 - 198, 2000/09

no abstracts in English

Oral presentation

Progress of engineering design in IFMIF-EVEDA project

Wakai, Eiichi; Kikuchi, Takayuki; Hirano, Michiko; Ida, Mizuho; Niitsuma, Shigeto; Kimura, Haruyuki; Nishitani, Takeo; Yamamoto, Michiyoshi; Matsumoto, Hiroshi; Sugimoto, Masayoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Activities summary on lithium target system and test facilities in IFMIF/EVEDA Project, 7; Engineering design of lithium target and post irradiation examination facilities in IFMIF

Sugimoto, Masayoshi; Wakai, Eiichi; Kanemura, Takuji; Kikuchi, Takayuki; Ida, Mizuho*; Watanabe, Kazuyoshi*; Niitsuma, Shigeto*; Yamamoto, Michiyoshi*; Yutani, Toshiaki*; Hirano, Michiko*

no journal, , 

The International Fusion Materials Irradiation Facility - Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) is a EU an Japan collaborative project under the framework of the Broader Approach activities for fusion energy development and, after the Intermediate Engineering Design Report has been completed in 2013, the validation test tasks have been conducted up to 2015. About the tasks in charge of Japan were completed in March and now we continue the evaluation of the testing results and examine how to reflect them to updated engineering design. In this report, we present the technical validity of the design based on the results of various validation tests and summarize the issues to be solved in future.

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