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JAEA Reports

Manufacture of substitutive assemblies for MONJU reactor decommissioning

Sakakibara, Hiroshi; Aoki, Nobuhiro; Muto, Masahiro; Otabe, Jun; Takahashi, Kenji*; Fujita, Naoyuki*; Hiyama, Kazuhiko*; Suzuki, Hirokazu*; Kamogawa, Toshiyuki*; Yokosuka, Toru*; et al.

JAEA-Technology 2020-020, 73 Pages, 2021/03

JAEA-Technology-2020-020.pdf:8.26MB

The decommissioning is currently in progress at the prototype fast breeder reactor Monju. Fuel assemblies will be taken out of its core for the first step of the great task. Fuel assemblies stand on their own spike plugged into a socket on the core support plate and support with adjacent assemblies through their housing pads each other, resulting in steady core structure. For this reason, some substitutive assemblies are necessary for the purpose of discharging the fuel assemblies of the core. Monju side commissioned, therefore, Plutonium Fuel Development Center to manufacture the substitutive assemblies and the Center accepted it. This report gives descriptions of design, manufacture, and shipment in regard to the substitutive assemblies.

Journal Articles

Emergent spin-1 Haldane gap and ferroelectricity in a frustrated spin-$$frac{1}{2}$$ ladder

Ueda, Hiroshi*; Onoda, Shigeki*; Yamaguchi, Yasuhiro*; Kimura, Tsuyoshi*; Yoshizawa, Daichi*; Morioka, Toshiaki*; Hagiwara, Masayuki*; Hagihara, Masato*; Soda, Minoru*; Masuda, Takatsugu*; et al.

Physical Review B, 101(14), p.140408_1 - 140408_6, 2020/04

 Times Cited Count:2 Percentile:16.85(Materials Science, Multidisciplinary)

Journal Articles

Investigation of hydrogen gas generation by radiolysis for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03

no abstracts in English

Journal Articles

Field-orientation dependence of low-energy quasiparticle excitations in the heavy-electron superconductor UBe$$_{13}$$

Shimizu, Yusei*; Kittaka, Shunichiro*; Sakakibara, Toshiro*; Haga, Yoshinori; Yamamoto, Etsuji; Amitsuka, Hiroshi*; Tsutsumi, Yasumasa*; Machida, Kazushige*

Physical Review Letters, 114(14), p.147002_1 - 147002_6, 2015/04

 Times Cited Count:30 Percentile:83.23(Physics, Multidisciplinary)

Journal Articles

Development of the volume reduction treatment of solid waste system by ultra-high frequency induction furnace

Sakakibara, Tetsuro; Aoyama, Yoshio; Yamaguchi, Hiromi; Sasaki, Naoto*; Nishikawa, Takeshi*; Murata, Minoru*; Park, J.*; Taniguchi, Shoji*; Fujita, Michiru*; Fukuda, Tomoyuki*; et al.

Proceedings of International Waste Management Symposium 2009 (WM '09) (CD-ROM), 15 Pages, 2009/03

The volume reduction treatment of solid waste system by ultra-high frequency induction furnace (UHFIF) was developed from FY2005 to FY2007. Basic data for melting performance were collected by non-radioactive experiments using the bench scale UHFIF with a crucible capacity of 10 liters. Based on the obtained data, engineering specifications were evaluated for a demonstration scale UHFIF with a crucible capacity of 30 liters. A new demonstration scale UHFIF was constructed and melting experiments of surrogate wastes were carried out by this furnace. It was confirmed that the demonstration scale UHFIF can melt ferrous metal, ceramics and aluminum all together and stabilize aluminum by oxidation to alumina. Density, chemical composition, and surface condition of the solidified substances were analyzed, and homogeneity of the solidified substances was confirmed. Melting behavior in the demonstration scale UHFIF was analyzed by computer simulation and simulation results agreed well with the experimental ones. From the design study for a full scale UHFIF with a crucible capacity of 100 liters, basic specifications were evaluated for the full scale UHFIF. Based on the obtained specification, melting behavior in the full scale UHFIF was analyzed by computer simulation.

JAEA Reports

Research and development for treatment and disposal technologies of TRU waste; JFY 2007 annual report

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Matsuda, Setsuro; Ichige, Satoru; Takahashi, Kuniaki; et al.

JAEA-Research 2008-082, 84 Pages, 2008/11

JAEA-Research-2008-082.pdf:2.52MB
JAEA-Research-2008-082(errata).pdf:0.15MB

Based on Japanese governmental policy and general scheme, research and development of geological disposal technology for TRU waste has been proceeding to improve reliability of the safety assessment of the co-locational disposal of TRU waste and of HLW, to expand the basement of generic safety assessment, and to develop the alternative technology to cope with the broad geologic environment of Japan. Japan Atomic Energy Agency is dealing with the assignments in the governmental generic scheme. We report here the progress of the studies at the end of H19 (2007) fiscal year, which are (1) treatment and packaging of TRU waste including applicability of calcination for unpacking and sorting of wastes, characterization and inspection methodology of TRU waste, (2) mechanical assessment for the near-field structure including model development and preparation, introduction of hostrock creep model and coupling analysis of deformation of hostrock and engineered barrier. (3) performance assessment of the disposal system including data acquisition and preparation on radionuclides migration, cementitious material alteration, bentonite and hostrock alteration with alkaline solution and nitrate effect, and (4) alternative technology development including decomposition of nitrate.

Journal Articles

Extended steady-state and high-beta regimes of net-current free heliotron plasmas in the Large Helical Device

Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Muto, Takashi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.

Nuclear Fusion, 47(10), p.S668 - S676, 2007/10

 Times Cited Count:34 Percentile:74.68(Physics, Fluids & Plasmas)

The performance of net-current free heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fuelling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an internal diffusion barrier (IDB) by a combination of efficient pumping of the local island divertor function and core fuelling by pellet injection has realized a super dense core as high as 5$$times$$10$$^{20}$$ m$$^{-3}$$, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5% and a discharge duration of 54 min with a total input energy of 1.6 GJ (490 kW on average) are also highlighted. The progress of LHD experiments in these two years is overviewed by highlighting IDB, high-beta and long pulse.

Journal Articles

Extended steady-state and high-beta regimes of net-current free heliotron plasmas in the large helical device

Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Muto, Takashi*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 12 Pages, 2007/03

The performance of net-current free Heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fueling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an Internal Diffusion Barrier (IDB) by combination of efficient pumping of the local island divertor function and core fueling by pellet injection has realized a super dense core as high as 5$$times$$10$$^{20}$$m$$^{-3}$$, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5 % and a discharge duration of 54-min. with a total input energy of 1.6 GJ (490 kW in average) are also highlighted. The progress of LHD experiments in these two years is overviewed with highlighting IDB, high $$beta$$ and long pulse.

Journal Articles

Observation of localized oscillations at ${it m/n}$=2/1 rational surface during counter neutral beam injection in the large helical device

Isayama, Akihiko; Inagaki, Shigeru*; Watanabe, Kiyomasa*; Narushima, Yoshiro*; Sakakibara, Satoru*; Funaba, Hisamichi*; Ida, Katsumi*; Nagayama, Yoshio*; Yamada, Hiroshi*; Kawahata, Kazuo*; et al.

Plasma Physics and Controlled Fusion, 48(1), p.L45 - L55, 2006/04

 Times Cited Count:12 Percentile:40.13(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Investigation of Radioactive Inventory in the TRU Solid Wastes Generated from the Tokai Reprocessing Plant

Sakakibara, Tetsuro; Tsutomu, Tanabe,; Takahashi, Kuniaki; Akutsu, Shigeru; Kojima, Hiroshi; Sakashita, Akira*; Kuroda, Kazuhiko*

Proceedings of International Waste Management Symposium 2005 (WM 2005), 0 Pages, 2005/00

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

JAEA Reports

Proceedings 4th Tsuruga International Energy Forum

Sakakibara, Yasuhide; IKEDA, Hiroshi; Yokota, Yoshio; Kitabata, Takuya; Yamaguchi, Toshihiko

JNC TN4200 2004-001, 317 Pages, 2004/08

JNC-TN4200-2004-001.pdf:24.97MB

None

Journal Articles

Achievement of high fusion triple product, steady-state sustainment and real-time NTM stabilization in high-$$beta_p$$ ELMy H-mode discharges in JT-60U

Isayama, Akihiko; Kamada, Yutaka; Hayashi, Nobuhiko; Suzuki, Takahiro; Oikawa, Toshihiro; Fujita, Takaaki; Fukuda, Takeshi; Ide, Shunsuke; Takenaga, Hidenobu; Ushigusa, Kenkichi; et al.

Nuclear Fusion, 43(10), p.1272 - 1278, 2003/10

 Times Cited Count:130 Percentile:95.99(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Magnetic, elastic, transport and fermi surface properties of a ferromagnetic compound UGa$$_{2}$$

Homma, Tetsuo; Yamamoto, Etsuji; Haga, Yoshinori; Settai, Rikio*; Araki, Shingo*; Inada, Yoshihiko*; Takeuchi, Tetsuya*; Kuwahara, Keitaro*; Amitsuka, Hiroshi*; Sakakibara, T.*; et al.

Physica B; Condensed Matter, 281-282, p.195 - 196, 2000/06

 Times Cited Count:2 Percentile:15.84(Physics, Condensed Matter)

no abstracts in English

Oral presentation

Evaluation of radioactivity in wastes from Tokai reprocessing plant, 4; Correlation between Tc-99 and Cs-137, 1

Sakakibara, Tetsuro; Kohanawa, Osamu; Akutsu, Shigeru; Kojima, Hiroshi; Sakashita, Akira*; Kuroda, Kazuhiko*; Kino, Kenichiro*; Saigusa, Moriyuki*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of radioactivity in wastes from Tokai reprocessing plant, 5; Correlation between activation products and Co-60, 1

Kino, Kenichiro*; Saigusa, Moriyuki*; Sakashita, Akira*; Kuroda, Kazuhiko*; Sakakibara, Tetsuro; Kohanawa, Osamu; Akutsu, Shigeru; Kojima, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Change of "effective plasma boundary" due to beta value in LHD divertor discharges

Watanabe, Kiyomasa*; Suzuki, Yasuhiro*; Yamaguchi, Taiki; Narihara, Kazumichi*; Tanaka, Kenji*; Tokuzawa, Tokihiko*; Yamada, Ichihiro*; Sakakibara, Satoru*; Morisaki, Tomohiro*; Nakajima, Noriyoshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of the volume reduction treatment system of radioactive waste by the ultra-high frequency induction furnace, 4; Outline of the demonstration system

Yamaguchi, Hiromi; Miyamoto, Yasuaki; Sakakibara, Tetsuro; Hanamoto, Yukio; Aoyama, Yoshio; Sasaki, Nao*; Nishikawa, Tsutomu*; Murata, Minoru*; Muroi, Masayuki*; Park, J.*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of the volume reduction treatment system of radioactive waste by the ultra-high frequency induction furnace,5; Demonstration experiment, Melting performance verification

Yamaguchi, Hiromi; Miyamoto, Yasuaki; Sakakibara, Tetsuro; Hanamoto, Yukio; Aoyama, Yoshio; Sasaki, Nao*; Nishikawa, Tsutomu*; Murata, Minoru*; Muroi, Masayuki*; Park, J.*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of the volume reduction treatment system of radioactive waste by the ultra-high frequency induction furnace,6; Demonstration experiment, Non-radioactive tracer experiment

Aoyama, Yoshio; Yamaguchi, Hiromi; Miyamoto, Yasuaki; Sakakibara, Tetsuro; Hanamoto, Yukio; Sasaki, Nao*; Nishikawa, Tsutomu*; Murata, Minoru*; Muroi, Masayuki*; Park, J.*; et al.

no journal, , 

no abstracts in English

Oral presentation

The Development of radioactive waste volume reduction treatment system by ultra-high frequency induction furnace, 7; Demonstration experiment, Incineration and melting performance test

Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.

no journal, , 

no abstracts in English

27 (Records 1-20 displayed on this page)