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Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count:62 Percentile:96.39(Nuclear Science & Technology)no abstracts in English
Kawamura, Yoshinori; Iwai, Yasunori; Nakamura, Hirofumi; Hayashi, Takumi; Yamanishi, Toshihiko; Nishi, Masataka
Fusion Science and Technology, 48(1), p.654 - 657, 2005/07
Times Cited Count:3 Percentile:24.17(Nuclear Science & Technology)Adding some amount of hydrogen to the helium sweep gas is effective for tritium extraction from blanket, but it causes permeation of tritium to a cooling system. In the design study of a demonstration reactor in JAERI, tritium leakage has been estimated to be about 20% of bred tritium under typical sweep gas conditions. If these tritiums are recovered under the ITER-WDS condition, tritium leakage limitation has to be less than 0.3% of typical case. Water vapor addition to the sweep gas is effective not only for blanket tritium extraction but also for permeation prevention. The reaction rate of isotope exchange is larger than the case of H, and the equilibrium constant is also expected to be about 1.0. When the H/T ratio is 100, tritium inventory of breeder material is larger than the case of H addition. However it is not so large. In case of HO sweep, separation of tritiated water from helium seems to be easyer, but the process that changes HTO to HT is necessary.
Enoeda, Mikio; Hatano, Toshihisa; Tsuchiya, Kunihiko; Ochiai, Kentaro; Kawamura, Yoshinori; Hayashi, Kimio; Nishitani, Takeo; Nishi, Masataka; Akiba, Masato
Fusion Science and Technology, 47(4), p.1060 - 1067, 2005/05
Times Cited Count:5 Percentile:35.66(Nuclear Science & Technology)Japan Atomic Energy Research Institute (JAERI) has been assigned as a leading institute for developing the solid breeder blanket in the long-term research program of fusion blankets in Japan, which was approved by the Fusion Council of Japan in 1999. In accordance with the long term research program, element technology development of solid blanket has been performed at JAERI and showed significant progress. Based on the achievement of the element technology development, the development phase is now stepping further to the engineering development phase. This paper presents the major achievements of the element technology development of solid breeder blanket in JAERI.
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count:4 Percentile:30.44(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of LiTiO and other breeders, fabrication technology developments and characterization of the LiTiO and LiSiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.
Nishitani, Takeo; Ochiai, Kentaro; Klix, A.; Verzilov, Y. M.; Sato, Satoshi; Yamauchi, Michinori*; Nakao, Makoto*; Hori, Junichi; Enoeda, Mikio
Proceedings of 20th IEEE/NPSS Symposium on Fusion Engineering (SOFE 2003), p.454 - 457, 2003/10
no abstracts in English
Kosaku, Yasuo; Kuroda, Toshimasa*; Enoeda, Mikio; Hatano, Toshihisa; Sato, Satoshi; Sato, Shinichi*; Osaki, Toshio*; Miki, Nobuharu*; Akiba, Masato
JAERI-Tech 2003-058, 69 Pages, 2003/06
The design of the breeding blanket in ITER applies pebble bed breeder in tube (BIT) surrounded by multiplier pebble bed. It is assumed to use the same module support mechanism and coolant manifolds and coolant system as the shielding blankets. This work focuses on the verification of the design of the breeding blanket, from the viewpoints which is especially unique to the pebble bed type breeding blanket, such as, tritium breeding performance, tritium inventory and release behavior and thermo-mechanical performance of the ITER breeding blanket.
Seki, Masahiro; Yamanishi, Toshihiko; Shu, Wataru; Nishi, Masataka; Hatano, Toshihisa; Akiba, Masato; Takeuchi, Hiroshi; Nakamura, Kazuyuki; Sugimoto, Masayoshi; Shiba, Kiyoyuki; et al.
Fusion Science and Technology, 42(1), p.50 - 61, 2002/07
Times Cited Count:5 Percentile:34.51(Nuclear Science & Technology)Latest status on development of long-term fusion nuclear technologies at JAERI is overviewed. A tritium processing system for the ITER and DEMO reactors was designed and basic technologies for each component of this system was demonstrated successfully by an operation of the integrated system for one month. An ultra-violet laser with a wave length of 193 nm was found quite effective for removing tritium from in-vessel components of D-T fusion reactors. Blanket technologies have been developed for the Test Blanket Module of the ITER and for advanced blankets for DEMO reactors. This blanket is composed of LiTiO breeder pebbles and neutron multiplier Be pebbles, contained in a box structures made of a reduced activation ferritic steel F82H. Mechanical properties of F82H under neutron irradiation up to 50 dpa were obtained in a temperature range from 200 to 500C. Design of the International Fusion Materials Irradiation Facility (IFMIF) has been developed so as to obtain engineering data for candidate materials for DEMO reactors, under neutron irradiation up to 100-200 dpa.
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
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.
Takatsu, Hideyuki; Kawamura, Hiroshi; Tanaka, Satoru*
Fusion Engineering and Design, 39-40, p.645 - 650, 1998/09
Times Cited Count:17 Percentile:77.73(Nuclear Science & Technology)no abstracts in English
Nakahira, Masataka; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki
JAERI-Tech 95-035, 20 Pages, 1995/07
no abstracts in English
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Journal of Nuclear Materials, 138, p.31 - 35, 1986/00
Times Cited Count:63 Percentile:97.95(Materials Science, Multidisciplinary)no abstracts in English
Furukawa, Kazuo; *;
Journal of Nuclear Science and Technology, 18(1), p.79 - 81, 1981/00
Times Cited Count:25 Percentile:95.65(Nuclear Science & Technology)no abstracts in English