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Konishi, Satoshi*; Enoeda, Mikio
Purazuma, Kaku Yugo Gakkai-Shi, 90(6), p.332 - 337, 2014/06
Test Blanket Module (TBM) program is to evaluate important functions of prototypical modules of DEMO breeding blankets in the real DT fusion plasma environment of ITER. Therefore, it is regarded as one of the most important milestones toward DEMO blanket. Japan is proposing a Water Cooled Ceramic Breeder (WCCB) TBM as the primary option of TBM program. Japan Atomic Energy Agency (JAEA) is performing the development of the WCCB blanket as the candidate breeding blanket of Japan, with a collaboration of universities and National Institute for Fusion Science (NIFS). Regarding the TBM development, the engineering R and Ds are ongoing, aiming at the demonstration of fabrication technology and structural integrity of the full size mockup of the WCCB TBM. Regarding the test blanket module fabrication technology development, the real scale back wall mockup was successfully fabricated. Also, the design activities are being performed to show the soundness under various loading conditions of electromagnetic force and thermo-mechanical loading. The evaluation of shutdown dose rate behind the TBM test port is also carried out as one of most important design requirement. Furthermore, key technologies toward DEMO blanket, such as, the development of advanced breeder and multiplier pebbles for DEMO blanket, fabrication technology development of Li rich Li
TiO
pebble and BeTi pebble was performed.
Hasegawa, Akira*; Tsuchiya, Kunihiko; Ishitsuka, Etsuo
Nihon Genshiryoku Gakkai-Shi, 47(8), p.536 - 544, 2005/08
no abstracts in English
Department of Fusion Engineering Research; Department of Materials Science
JAERI-Review 2005-012, 143 Pages, 2005/03
JAERI-Review-2005-012.pdf:11.74MB
no abstracts in English
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：101 Percentile：93.45(Physics, Fluids & Plasmas)no abstracts in English
Li-enriched breeding blanket with LiTiO/Be/F82H assembly using D-T neutronsOchiai, Kentaro; Klix, A.; Hori, Junichi; Morimoto, Yuichi*; Wada, Masayuki*; Nishitani, Takeo
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1147 - 1150, 2002/08
Thermal blanket type as one of conceptual designs for DEMO-fusion blanket is proposed. We have irradiated the trial blanket assembly which was stratified 95-% enriched Li2TiO3,F82H and beryllium block using Fusion Neutron Source (FNS) and verified the accuracy of these parameters by measurements of tritium and gamma-ray emitted from samples of95-% enriched Li2TiO3 and F82H. We have used the liquid scintillated counter as the method of tritium measurement. Activation foils, NE213, Si-SBD and Fission chamber have usedto measure neutron fluence. Moreover, we have concurrently measured the gamma rays of 56Mn, 54Mn, 187W and 51Cr was produced by 56Fe(n,p), 54Fe(n,p), 186W(n,g), 52Cr(n,2n) and 50Cr(n,g) in F82H. We have used the JENDL Fusion File library and MCNP to verify the accuracy tritium-production rate and 56Mn, 54Mn, 187W and 51Cr. From the results of above experiments, MCNP that uses the JENDL-FF nuclear data library can predict the nuclear parameters such as TPR, Nb, 56Mn, In and 54Mn in the test assemblies within an accuracy of 10%.
Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka; Kakuta, Toshiya*
Fusion Science and Technology, 41(3), p.1035 - 1039, 2002/05
To establish the nuclear fusion reactor, tritium bred in the breeder blanket of the fusion reactor must be recovered effectively. The present authors have proposed the blanket tritium recovery system using the hydrogen pump with solid electrolyte membrane. Hydrogen isotopes including tritium can be separated from helium purge gas of the breeder blanket by the protonic conductor membrane which pumps out hydrogen isotopes selectively by applying a few potential difference between its faces. Perovskite-type ceramic such as SrCe
Yb
O
, is one of the candidate protonic conductor for hydrogen pump and its ionic hydrogen transportation properties have been investigated. Deuterium transportation properties have also been investigated to understand the isotope effect. Through the investigation up to now, the basic hydrogen isotope transportation property of SrCeYbO, its technical feasibility, and issues for further development toward the practical devices were revealed.
TiO pebble-bedTsuchiya, Kunihiko; Kikukawa, Akihiro*; Yamaki, Daiju; Nakamichi, Masaru; Enoeda, Mikio; Kawamura, Hiroshi
Fusion Engineering and Design, 58-59, p.679 - 682, 2001/11
Times Cited Count：8 Percentile：52.36(Nuclear Science & Technology)no abstracts in English
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：24 Percentile：83.28(Nuclear Science & Technology)no abstracts in English
Nishitani, Takeo; Kutsukake, Chuzo; Hori, Junichi
Purazuma, Kaku Yugo Gakkai-Shi, 77(6), p.609 - 610, 2001/06
no abstracts in English
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
Konishi, Satoshi; Asaoka, Yoshiyuki*; Hiwatari, Ryoji*; Okano, Kunihiko*
Purazuma, Kaku Yugo Gakkai-Shi, 76(12), p.1309 - 1312, 2000/12
no abstracts in English
Kawamura, Yoshinori; Konishi, Satoshi; Nishi, Masataka
Journal of Nuclear Science and Technology, 37(6), p.536 - 542, 2000/06
no abstracts in English
*; Kuroda, Toshimasa*; Enoeda, Mikio
JAERI-Tech 98-059, 75 Pages, 1999/01
no abstracts in English
Kuroda, Toshimasa*; Enoeda, Mikio; *; *; Sato, Shinichi*; Osaki, Toshio*; Furuya, Kazuyuki; Hatano, Toshihisa; Sato, Satoshi; Takatsu, Hideyuki
JAERI-Tech 98-051, 71 Pages, 1998/11
no abstracts in English
Enoeda, Mikio; Takatsu, Hideyuki
Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.463 - 467, 1998/05
no abstracts in English
Noda, Kenji
JAERI-Conf 98-006, 286 Pages, 1998/03
no abstracts in English
ZrO packed bedKawamura, Yoshinori; Enoeda, Mikio; Okuno, Kenji
Fusion Engineering and Design, 39-40, p.713 - 721, 1998/00
Times Cited Count：8 Percentile：57.28(Nuclear Science & Technology)no abstracts in English
*; Sato, Satoshi; Enoeda, Mikio; Takatsu, Hideyuki; *; *; *
Fusion Technology 1998, 2, p.1333 - 1336, 1998/00
no abstracts in English
Kawamura, Hiroshi; Tsuchiya, Kunihiko; Nakamichi, Masaru; Fujita, J.*; Sagawa, Hisashi; Nagao, Yoshiharu; Y.Gohar*; ; Saito, Takashi; ; et al.
Fusion Technology 1998, 2, p.1289 - 1292, 1998/00
no abstracts in English
Kawamura, Yoshinori; Okuno, Kenji; Nishikawa, Masabumi*
Proceedings of 4th International Workshop on Ceramic Breeder Blanket Interface (CBBI-4), p.235 - 248, 1995/10
no abstracts in English
