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Journal Articles

Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex, 2; Neutron scattering instruments

Nakajima, Kenji; Kawakita, Yukinobu; Ito, Shinichi*; Abe, Jun*; Aizawa, Kazuya; Aoki, Hiroyuki; Endo, Hitoshi*; Fujita, Masaki*; Funakoshi, Kenichi*; Gong, W.*; et al.

Quantum Beam Science (Internet), 1(3), p.9_1 - 9_59, 2017/12

The neutron instruments suite, installed at the spallation neutron source of the Materials and Life Science Experimental Facility (MLF) at the Japan Proton Accelerator Research Complex (J-PARC), is reviewed. MLF has 23 neutron beam ports and 21 instruments are in operation for user programs or are under commissioning. A unique and challenging instrumental suite in MLF has been realized via combination of a high-performance neutron source, optimized for neutron scattering, and unique instruments using cutting-edge technologies. All instruments are/will serve in world-leading investigations in a broad range of fields, from fundamental physics to industrial applications. In this review, overviews, characteristic features, and typical applications of the individual instruments are mentioned.

Journal Articles

Thermal-hydraulics technological strategy roadmap that improves safety of LWRs

Arai, Kenji*; Umezawa, Shigemitsu*; Oikawa, Hirohide*; Onuki, Akira*; Nakamura, Hideo; Nishi, Yoshihisa*; Fujii, Tadashi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(3), p.161 - 166, 2016/03

no abstracts in English

Journal Articles

Management of radioactive materials for the disassembly of JT-60U fusion tokamak device

Sukegawa, Atsuhiko; Miya, Naoyuki; Oikawa, Akira

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 8 Pages, 2011/10

The radioactivities on the materials of JT-60U fusion device, which decommissioning is underway toward the upgraded superconducting tokamak machine, have been evaluated by calculation and measurements on the specimens of the structure materials and the components. In the induced activities on those materials, the highest activation on the material was stainless steel. The essential nuclide was $$^{60}$$Co in the stainless steels. The stainless steel 316 of about 35 tons constitutes the base of interiorities as a first wall on the vacuum vessel in JT-60U. For the management of radioactive materials, the evaluation for the steels with the activated nuclides is important. The activated structure materials are kept in the controlled area in the JT-60 facilities, according to the criteria for handling activated materials by the defined domestic government.

Journal Articles

Storage and safety management of radioactive components for disassembly of JT-60 tokamak device

Nishiyama, Tomokazu; Okano, Fuminori; Miyo, Yasuhiko; Kubo, Hirotaka; Miya, Naoyuki; Oikawa, Akira; Sasajima, Tadayuki; Sakasai, Akira

Heisei-22-Nendo Kumamoto Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 5 Pages, 2011/03

no abstracts in English

Journal Articles

Molecular dynamics free energy calculations to assess the possibility of water existence in protein nonpolar cavities

Oikawa, Masataka; Yonetani, Yoshiteru

Biophysical Journal, 98(12), p.2974 - 2983, 2010/06

 Times Cited Count:9 Percentile:23.53(Biophysics)

Journal Articles

Estimation of low level waste by a regulatory clearance in JT-60U fusion device

Sukegawa, Atsuhiko; Oikawa, Akira; Miya, Naoyuki; Fujita, Takaaki

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04

The low level waste of JT-60U fusion device has been estimated by a regulatory clearance. The JT-60U consists of the heating devices such as neutral beam injectors and radio frequency systems, the main devices including the vacuum vessel and the coils, and the diagnostic devices in the torus hall. Those structure materials of the JT-60U device include copper, stainless steels, carbon steel, high manganese steel, inconel 625, ferritic steel, and lead. The gross weight of the device is about 6,400 tons. Radiation transport calculations are performed using 1D code ANISN. In the activation calculations, ACT-4 was employed. The stainless steels of about 50 tons are used for the base of the first wall on the vacuum vessel in JT-60U. For the low level waste management, the evaluation for the steels with the activated nuclides is important. IAEA RS-G-1.7 is applied to the clearance level for the structures of the activated materials. The activated level of the material with $$^{60}$$Co takes about 45 years until less than the clearance level.

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:22.95(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Evaluation of radiation shielding, nuclear heating and dose rate for JT-60 superconducting modification

Morioka, Atsuhiko; Sakasai, Akira; Masaki, Kei; Ishida, Shinichi; Miya, Naoyuki; Matsukawa, Makoto; Kaminaga, Atsushi; Oikawa, Akira

Fusion Engineering and Design, 63-64, p.115 - 120, 2002/12

 Times Cited Count:11 Percentile:58.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium experience in JT-60 operation

Oikawa, Akira; Miya, Naoyuki

Purazuma, Kaku Yugo Gakkai-Shi, 78(12), p.1308 - 1312, 2002/12

Tritium experience over decade in DD operation of JT-60 is summarized.Effluent of tritium in vacuum exhaust through the stack to environment always remains a level below detectable levels. Tritium concentration of drain is also below the limit of regurations of the local agreement amd the law. For a scheduled maintenance work of the in-vessel components, following an annual deuterium plasma discharge campaign, a 4-week no-deuterium plasma discharge campaign and the succeeded ventilation by room air allow to reduce tritium concentration on the surface of in-vessel components. A cooperative endeavour is underway for analysis of tritium behavior in JT-60.

Journal Articles

The Kinetics of Fe and Ca for the development of radiation-induced apoptosis by micro-PIXE imaging

Harada, Satoshi*; Tamakawa, Yoshiharu*; Ishii, Keizo*; Tanaka, Akira*; Sato, Takahiro; Matsuyama, Shigeo*; Yamazaki, Hiromichi*; Kamiya, Tomihiro; Sakai, Takuro; Arakawa, Kazuo; et al.

Nuclear Instruments and Methods in Physics Research B, 189(1-4), p.437 - 442, 2002/04

 Times Cited Count:1 Percentile:12.5(Instruments & Instrumentation)

To study the interactions between the induction of radiation-induced apoptosis and trace elements kinetics, human leukemia cells were irradiated in vitro by $$^{60}$$Co $$gamma$$ rays, after which the cells were evaluated for the detection of apoptosis and trace element imaging was carried out. The frequency of apoptosis was obtained by microscopic assay using TUNEL staining. The trace element distribution in the cell was determined by micro-PIXE. In the early phase of apoptosis, the maximum level of Fe accumulation was observed in the cell stroma. In the mid to end phase, Fe accumulation was diminished, and instead, Ca accumulation increased and Zn decreased in the nucleus. There appear to be two steps for the development of apoptosis: (1) the signaling from cell stroma to nucleus by Fe or an Fe-containing enzyme; and (2) the degeneration of the nucleus by Ca-dependent enzyme, and release of Zn from digested nucleus. Those strong accumulations may be new markers for apoptosis.

Journal Articles

JAERI Takasaki in-air micro-PIXE system for various applications

Sakai, Takuro; Kamiya, Tomihiro; Oikawa, Masakazu*; Sato, Takahiro; Tanaka, Akira*; Ishii, Keizo*

Nuclear Instruments and Methods in Physics Research B, 190(1-4), p.271 - 275, 2001/09

 Times Cited Count:66 Percentile:95.98(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Concept of JT-60 Super Upgrade

Ninomiya, Hiromasa; Kamada, Yutaka; Miya, Naoyuki; *; *; Oikawa, Akira; Sakasai, Akira; Takahashi, Yoshikazu; Takizuka, Tomonori; ; et al.

15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 1, 0, p.374 - 377, 1993/00

no abstracts in English

Journal Articles

Conceptual design study of nuclear shielding for the steady state tokamak device JT-60SU

Miya, Naoyuki; ; *; Nakamura, Hiroo; Ushigusa, Kenkichi; Oikawa, Akira; Nishitani, Takeo; ; *; Nakagawa, S.*; et al.

Fusion Engineering and Design, 23, p.351 - 358, 1993/00

 Times Cited Count:1 Percentile:17.88(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Preliminary design study of a steady state tokamak device

Miya, Naoyuki; *; Ushigusa, Kenkichi; Oikawa, Akira; Imai, Tsuyoshi; ; Nishitani, Takeo; Matsuzaki, Yoshimi; Kuriyama, Masaaki;

JAERI-M 92-140, 156 Pages, 1992/09

JAERI-M-92-140.pdf:4.19MB

no abstracts in English

Journal Articles

Conceptual design of the Steady State Tokamak Reactor(SSTR)

Kikuchi, Mitsuru; Seki, Yasushi; Oikawa, Akira; Ando, Toshinari; Ohara, Yoshihiro; Nishio, Satoshi; Seki, Masahiro; Takizuka, Tomonori; Tani, Keiji; Ozeki, Takahisa; et al.

Fusion Engineering and Design, 18, p.195 - 202, 1991/00

 Times Cited Count:8 Percentile:66.05(Nuclear Science & Technology)

no abstracts in English

Journal Articles

History and organization of fusion research and development in Japan

Oikawa, Akira

Fusion Technology, 17, p.232 - 235, 1990/03

no abstracts in English

Journal Articles

Construction and testing of JT-60

; ; Oikawa, Akira; Miya, Naoyuki; ; Ozeki, Takahisa; ; Kunieda, Shunsuke; ;

Fusion Engineering and Design, 5, p.9 - 25, 1987/00

 Times Cited Count:4 Percentile:44.92(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Characteristics on tritium release during plasma operation on JT-60U

Oikawa, Akira; Nakamura, Hirofumi; Kaminaga, Atsushi; Masaki, Kei; Yamazaki, Takeshi*; Tanabe, Tetsuo*

no journal, , 

During DD plasma discharges, tritium produced by the discharges are accumulated on in-vessel components including a carbon based first wall. A few week of detritiation campaign with no-deuterium plasma discharges take place before the scheduled maintenance work on JT-60U. It is recently found that a longer pulse and higher power electron cyclotron resonance heating(ECRH) with deuterium on JT-60U also provides effectively detritiation of the plasma facing components, simultaneously improving confinement and supressing neutron yield. This approach could help control tritium inventory under plasma discharges on fusion devices. The enhanced radiation power is expected to cause the particle recycling and resultantly enhanced detritiation. The higher plasma current with higher electron density with the longer pulse of ECR power injection enhances the detritiation capability.

Oral presentation

Estimation on activation of JT-60 Tokamak device for clearance

Morioka, Atsuhiko; Oikawa, Akira; Miya, Naoyuki

no journal, , 

no abstracts in English

30 (Records 1-20 displayed on this page)