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Journal Articles

Superior TRIP effect in a duplex stainless steel and its mechanism studied by ${it in situ}$ neutron diffraction experiments

Tsuchida, Noriyuki*; Fujita, Akinori*; Hirakawa, Naoki*; Hamada, Junichi*; Ishimaru, Eiichiro*; Gong, W.; Kawasaki, Takuro; Harjo, S.

Materials Characterization, 236, p.116436_1 - 116436_13, 2026/06

 Times Cited Count:1 Percentile:0.00(Materials Science, Multidisciplinary)

Journal Articles

Welding technology on sector assembly of the JT-60SA vacuum vessel

Shibama, Yusuke; Okano, Fuminori; Yagyu, Junichi; Kaminaga, Atsushi; Miyo, Yasuhiko; Hayakawa, Atsuro*; Sagawa, Keiich*; Mochida, Tsutomu*; Morimoto, Tamotsu*; Hamada, Takashi*; et al.

Fusion Engineering and Design, 98-99, p.1614 - 1619, 2015/10

 Times Cited Count:4 Percentile:28.20(Nuclear Science & Technology)

The JT-60SA vacuum vessel (150 tons) is a double wall torus structure and the maximum major radius of 5.0 m and height of 6.6 m. The manufacturing design concept is that the vessel is split in the 10 toroidal sectors manufactured at factory, and assembled on-site; seven of the 40-degree sectors, two of the 30-degree beside final one, and the final of the 20-degree. The final sector is assembled with the VV thermal shield and toroidal field magnets into the 340-degree as prepared in one sector. Sectors are temporally fitted on-site and adjusted one over the other before the assembly. After measurement of the dimensions and the reference, these sectors are transferred onto the cryostat base. First, three 80-degree sectors are manufactured with mating each 40-degree sector by direct joint welding. The rest sectors including the final sector are jointed with splice plates. Welding manipulator and its guide rails are used for these welding. In this paper, the detail of the VV sectors assembly including the final sector is explained. Welding technologies to joint the two of 40-degree sectors are reported with the present manufacturing status and the welding trial on the vertical stub with the partial mock-up of the final sector are discussed with the assembly process.

JAEA Reports

Lead-Bismuth Transfer Behavior Preliminary Test in Liquid Sodium; Effect of Test Temperature and Amount of Lead-Bismuth on Reaction Behavior

Saito, Junichi; Sagawa, Norihiko; Ohno, Shuji; Hamada, Hirotsugu; Miyahara, Shinya

JNC TN9400 2004-059, 133 Pages, 2004/09

JNC-TN9400-2004-059.pdf:6.05MB

The simplified secondary sodium cooling system, in which utilized lead-bismuth eutectic is utilized as an intermediate coolant has been selected as one of candidate system for the "Feasibility Studies on Commercialized Fast Reactor System (Phase I)". The purpose of this study for the "FS (PhaseII)" is to understand transfer behavior of lead-bismuth in liquid sodium by experiment. The experiments which trickles liquid lead-bismuth into liquid sodium are carried out of under various test temperature and amount of lead-bismuth. The effects of test temperature and amount of lead-bismuth on reaction behavior of sodium and lead-bismuth are clarified from the experimental results. The obtained results from experiments are as follows. (1) The experiment under lower test temperature takes longer time for reaction between sodium and lead-bismuth than that under higher test temperature. It means that test temperature affects the reaction behavior between sodium and lead-bismuth. (2) The amount of dropping lead-bismuth affects an amount and kind of reaction products which are formed by reaction between sodium and lead-bismuth. (3) Reaction heat obtained from the experiments is similar to estimated reaction heat using formation enthalpy of BiNa3 which is one of dominant reaction products.

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

no abstracts in English

Journal Articles

Advanced fusion technologies developed for JT-60 superconducting Tokamak

Sakasai, Akira; Ishida, Shinichi; Matsukawa, Makoto; Akino, Noboru; Ando, Toshinari*; Arai, Takashi; Ezato, Koichiro; Hamada, Kazuya; Ichige, Hisashi; Isono, Takaaki; et al.

Nuclear Fusion, 44(2), p.329 - 334, 2004/02

 Times Cited Count:7 Percentile:21.89(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Charge-ordered state in single-crystalline CaFeO$$_{3}$$ thin film studied by X-ray anomalous diffraction

Akao, Tadahiro*; Azuma, Yusuke; Usuda, Manabu; Nishihata, Yasuo; Mizuki, Junichiro; Hamada, Noriaki*; Hayashi, Naoaki*; Terashima, Takahito*; Takano, Mikio*

Physical Review Letters, 91(15), p.156405_1 - 156405_4, 2003/10

 Times Cited Count:38 Percentile:80.43(Physics, Multidisciplinary)

X-ray anomalous diffraction, together with a band structure calculation, was employed to obtain a quantitative comprehension of the charge-ordering state in a single-crystalline CaFeO$$_{3}$$ thin film. The experimental results show a characteristic energy dispersion of the near inhibited reflection at 150, implying Fe atoms split into two distinct states. The energy dispersion is in good agreement with the calculated spectrum based on LDA+U scheme. The calculation reveals an electronic configuration of the Fe 3d orbital follows a localization in the oxygen orbital surrounds one of the distinct Fe atoms.

JAEA Reports

Lead-Bismuth Transfer Behavior Preliminary Test in Liquid Sodium

Saito, Junichi; Takai, Toshihide; Sagawa, Norihiko; Ohno, Shuji; Hamada, Hirotsugu; Miyahara, Shinya

JNC TN9400 2003-057, 87 Pages, 2003/06

JNC-TN9400-2003-057.PDF:24.73MB

The simplified secondary sodium cooling system utilized lead-bismuth eutectic as an intermediate coolant has been selected one of candidate system for the "Feasibility Studies on Commercialized Fast Reactor System (Phase I)". The purpose of this study for the "FS (Phase II)" is to understand transfer behavior of lead-bismuth in liquid sodium by experiment. From the experimental results the fundamental data are obtained for the feasibility evaluation of the simplified secondary sodium cooling system. Twice experiments which trickles liquid lead-bismuth into liquid sodium are carried out at 400 degress centigrade are obtained. (1) From the ICP analyses of L1-1 and L1-2 test, the lead concentration of sodium is higher than the bismuth concentration. This shows that the amount of dissolution of lead into liquid sodium was larger than that of bismuth. This result agrees with data of the previous solubility data in Pb-Na and Bi-Na binary system in sodium. The solid black particles observed in sodium contain a large amount of bismuth. (2) Temperature of liquid sodium rises when the drops of liquid lead-bismuth are added into liquid sodium. The total heating value calculated using temperature rises observed at several parts in equipment is 137 kJ/mol-LBE on L1-2 test. This heat of reaction is promising for leak detection of lead-bismuth into sodium. (3) Many black solid products are observed in sodium taken from L1-1 and L1-2 test apparatus. The reaction products taken from upper location in a sampling finger are very fine and the size was 5 ~ 10$$times$$10$$^{-6m.}$$Those from lower location increase in size and the size was 50 ~100$$times$$10-6m.

Journal Articles

3D Transport Theory Method Based on MOC for Analyzing Integral Dta of Transmutation

Takeda, Toshikazu*; Hamada, Yuzuru*; Kitada, Takanori*; Nishi, Hiroshi; Ishibashi, Junichi; Kitano, Akihiro

Proceedings of International Conference on Advanced Nuclear Energy and Fuel Cycle Systems (GLOBAL 2003) (CD-ROM), p.1005 - 1010, 2003/00

A new 3-D transport calculation method taking into account the heterogeneity of fuel assemblies has been developed by combining the characteristics method and the nodal transport method. In the axial direction the nodal transport method is applied, and the characteristics method is applied to take into account the radial heterogeneity of fuel assemblies. The numerical calculations have been performed to verify 2-D radial calculations of FBR assemblies and partial core calculations. Results are compared with the reference Monte-Carlo calculations. A good agreement has been achieved. It is shown that the present method has an advantage in calculating reaction rates in a small region.

Journal Articles

Self-regeneration of a Pd-perovskite catalyst for automotive emissions control

Nishihata, Yasuo; Mizuki, Junichiro; Akao, Takahiro; Tanaka, Hirohisa*; Uenishi, Mari*; Kimura, Mareo*; Okamoto, Tokuhiko*; Hamada, Noriaki*

Nature, 418(6894), p.164 - 167, 2002/07

 Times Cited Count:1076 Percentile:99.83(Multidisciplinary Sciences)

no abstracts in English

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:18 Percentile:75.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Test results of the SMES model coil; Cool-down and thermal characteristics

Hamada, Kazuya; Kato, Takashi; Kawano, Katsumi; ; ; ; Imahashi, Koichi*; Otsu, K.*; Tajiri, F.*; Ouchi, T.*; et al.

Teion Kogaku, 33(7), p.467 - 472, 1998/00

no abstracts in English

Oral presentation

Sector manufacturing and assembly of the JT-60SA vacuum vessel

Shibama, Yusuke; Okano, Fuminori; Yagyu, Junichi; Kaminaga, Atsushi; Miyo, Yasuhiko; Hayakawa, Atsuro*; Sagawa, Keiich*; Mochida, Tsutomu*; Morimoto, Tamotsu*; Hamada, Takashi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Self-regeneration of perovskite-based catalyst, 1; Crystal structure

Taniguchi, Masashi*; Kan, C. Y.*; Uenishi, Mari*; Tanaka, Hirohisa*; Matsumura, Daiju; Nishihata, Yasuo; Mizuki, Junichiro; Uozumi, Akifumi*; Hamada, Ikutaro*; Morikawa, Yoshitada*

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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