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Journal Articles

Application of virtual tour for online training safeguards exercises

Sekine, Megumi; Sukegawa, Hidetoshi; Ishikuro, Yasuhiro; Oyama, Koji; Obata, Takashi; Hayashi, Kazuhiko; Inoue, Naoko

Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 10 Pages, 2021/08

The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) developed the virtual tour of a reference nuclear facility. The developed virtual tour was applied to the Design Information Questionnaire (DIQ) workshop exercise for the online SSAC course held in November 2020 in connection with the IAEA safeguards-related regional training course. Also, it was applied to the Complementary Access (CA) exercise for the online workshop of the Nuclear Security and Safeguards Project under the Forum for Nuclear Cooperation in Asia (FNCA), held in February 2021. The workshop exercises have been implemented for in-person format however due to COVID-19 pandemic, a virtual tour was applied. The virtual tour was found to be a strong tool not only for online training as an alternative for a facility tour, but also considered to be more advantageous even for the in-person training. The developed virtual tour of a reference nuclear facility, going to shut down, can find potentially varied applications. The paper describes how to create a virtual tour of a reference research reactor facility for the DIQ and CA exercises respectively which have different learning objectives. It emphasizes how the features of the reference facility were captured and the challenges encountered to convey to the training participants the importance of providing the required design information while not being physically present at the facility. It also show the advantage of using the same virtual tour to describe the safeguards-related verification activities of a complementary access. Virtual tours can be applied to a variety of training.

JAEA Reports

Development of ITER CODAC compatible gyrotron local control system and its operation

Oshima, Katsumi; Oda, Yasuhisa; Takahashi, Koji; Terakado, Masayuki; Ikeda, Ryosuke; Hayashi, Kazuo*; Moriyama, Shinichi; Kajiwara, Ken; Sakamoto, Keishi

JAEA-Technology 2015-061, 65 Pages, 2016/03


In JAEA, an ITER relevant control system for ITER gyrotron was developed according to Plant Control Design Handbook. This control system was developed based on ITER CODAC Core System and implemented state machine control of gyrotron operation system, sequential timing control of gyrotron oscillation startup, and data acquisition. The operation of ITER 170 GHz gyrotron was demonstrated with ITER relevant power supply configuration. This system is utilized for gyrotron operation test for ITER procurement. This report describes the architecture of gyrotron operation system, its basic and detailed design, and recent operation results.

Journal Articles

Report of ITPA TG Meetings, 52

Shinohara, Koji; Hayashi, Nobuhiko; Isayama, Akihiko; Miyato, Naoaki; Urano, Hajime; Aiba, Nobuyuki

Purazuma, Kaku Yugo Gakkai-Shi, 91(12), p.797 - 800, 2015/12

no abstracts in English

Journal Articles

Integrated modelling of toroidal rotation with the 3D non-local drift-kinetic code and boundary models for JT-60U analyses and predictive simulations

Honda, Mitsuru; Satake, Shinsuke*; Suzuki, Yasuhiro*; Yoshida, Maiko; Hayashi, Nobuhiko; Kamiya, Kensaku; Matsuyama, Akinobu; Shinohara, Koji; Matsunaga, Go; Nakata, Motoki; et al.

Nuclear Fusion, 55(7), p.073033_1 - 073033_11, 2015/07

 Times Cited Count:5 Percentile:25.55(Physics, Fluids & Plasmas)

Journal Articles

Integrated modeling of toroidal rotation with the 3D non-local drift-kinetic code and boundary models for JT-60U analyses and predictive simulations

Honda, Mitsuru; Satake, Shinsuke*; Suzuki, Yasuhiro*; Yoshida, Maiko; Hayashi, Nobuhiko; Kamiya, Kensaku; Matsuyama, Akinobu; Shinohara, Koji; Matsunaga, Go; Nakata, Motoki; et al.

Proceedings of 25th IAEA Fusion Energy Conference (FEC 2014) (CD-ROM), 8 Pages, 2014/10

Journal Articles

Elaboration of the system based code concept; Activities in JSME and ASME, 1; Overview

Asayama, Tai; Miyagawa, Takayuki*; Dozaki, Koji*; Kamishima, Yoshio*; Hayashi, Masaaki*; Machida, Hideo*

Proceedings of 22nd International Conference on Nuclear Engineering (ICONE-22) (DVD-ROM), 7 Pages, 2014/07

This paper is the first one of the series of four papers that describe ongoing activities in the Japan Society of Mechanical Engineers (JSME) and the American Society of Mechanical Engineers (ASME) on the elaboration of the System Based Code (SBC) concept. A brief introduction to the SBC concept is followed by the technical features of structural evaluation methodologies that are based on the SBC concept. Also described is the ongoing collaboration of JSME and ASME at the Joint Task Group for System Based Code established in the ASME Boiler and Pressure Vessel Code Committee which is developing alternative rules for ASME B&PV Code Section XI Division 3, inservice inspection requirements for liquid metal reactor components.

Journal Articles

Development of ITER CODAC compatible gyrotron local control system and its operation

Oda, Yasuhisa; Oshima, Katsumi; Nakamoto, Takashi*; Hashimoto, Yasunori*; Yamamoto, Tsuyoshi; Hayashi, Kazuo*; Ikeda, Yukiharu; Ikeda, Ryosuke; Kajiwara, Ken; Takahashi, Koji; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 90(7), p.365 - 373, 2014/07

no abstracts in English

Journal Articles

Report on ITPA meetings, 45

Hayashi, Nobuhiko; Aiba, Nobuyuki; Isayama, Akihiko; Shinohara, Koji; Honda, Mitsuru

Purazuma, Kaku Yugo Gakkai-Shi, 90(6), p.352 - 355, 2014/06

no abstracts in English

Journal Articles

Report on ITPA (International Tokamak Physics Activity) meeting, 42

Yoshida, Maiko; Shinohara, Koji; Hayashi, Nobuhiko; Isayama, Akihiko; Kamiya, Kensaku

Purazuma, Kaku Yugo Gakkai-Shi, 89(12), p.887 - 889, 2013/12

ITPA (International Tokamak Physics Activity) meetings were held in Autumn 2013.

JAEA Reports

Immersion test in artificial water and evaluation of strength property on fuel cladding tubes irradiated in Fugen Nuclear Power Plant

Yamagata, Ichiro; Hayashi, Takehiro; Mashiko, Shinichi*; Sasaki, Shinji; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji

JAEA-Testing 2013-004, 23 Pages, 2013/11


In the accident of the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Co. accompanying the Great East Japan Earthquake, fuel assemblies kept in the spent fuel pool of reactor units 1-4, were exposed to the inconceivable environment such as falling and mixing of rubble, especially seawater were injected into unit 2-4. In order to evaluate the integrity of the fuel assemblies in spent fuel pools, and in the long-term storage after transported to the common storage pool, the immersion tests were performed using zircaloy-2 fuel cladding tubes irradiated in the advanced thermal reactor Fugen. The immersion liquid was prepared with doubling dilution of artificial seawater, which temperature was 80 $$^{circ}$$C and immersion time was about 336 hours, as assuming the situation of the pool. The results indicated zircaloy-2 cladding tubes had no significant corrosion and no influence on mechanical property by immersion tests with artificial seawater conditions of this work.

Journal Articles

A Sampling method of oriented small sample from fault cores for SEM observation

Shimada, Koji; Kametaka, Masao*; Nakayama, Kazuhiko; Seshimo, Kazuyoshi; Tanaka, Yoshihiro; Hayashi, Toshio*; Tanaka, Yukumo; Shimogama, Kota*; Okazaki, Kazuhiko*

Chishitsugaku Zasshi, 119(11), p.727 - 731, 2013/11

Staples for a stapler can be used as a frame of a small oriented sample taken from fragile and scarce fault gouge. The fault gouge was slotted for staples of an insert. Staples are a group of about ten or less ones holding right-angled three small surfaces. Pre-oriented staples set the slot would remove then presented for the SEM observation. Only a knife, some glues and simple equipment are needed for the method in the field or laboratories.

Journal Articles

Report of International Tokamak Physics Activity meeting, 40

Isayama, Akihiko; Asakura, Nobuyuki; Hayashi, Nobuhiko; Shinohara, Koji; Honda, Mitsuru; Oyama, Naoyuki

Purazuma, Kaku Yugo Gakkai-Shi, 89(6), p.430 - 433, 2013/06

no abstracts in English

Journal Articles

Full high-power modulation on a 170 GHz 1 MW ITER gyrotron with a triode magnetron injection gun

Kajiwara, Ken; Sakamoto, Keishi; Oda, Yasuhisa; Hayashi, Kazuo*; Takahashi, Koji; Kasugai, Atsushi

Nuclear Fusion, 53(4), p.043013_1 - 043013_5, 2013/04

 Times Cited Count:18 Percentile:64.77(Physics, Fluids & Plasmas)

Journal Articles

Tectonic shortening and coeval volcanism during the Quaternary, northeast Japan arc

Umeda, Koji; Ban, Masao*; Hayashi, Shintaro*; Kusano, Tomohiro

Journal of Earth System Science, 122(1), p.137 - 147, 2013/02

 Times Cited Count:6 Percentile:19.25(Geosciences, Multidisciplinary)

From a compilation and analysis of stratigraphy, radiometric age and data on erupted magma volumes, 176 eruptive episodes identified from 69 volcanoes so far, indicate that notable changes in eruption style, magma discharge rates and distribution of eruptive centers occurred around 1.0 Ma. Before ca. 1.0 Ma in northeast Japan, large-volume felsic eruptions were dominant, forming large calderas in the frontal arc, a region of low crustal strain rate. After ca. 1.0 Ma to the present, the calc-alkaline andesite magma eruptions in the frontal and rear arcs, synchronous with crustal shortening characterized by reverse faulting, resulting in stratovolcano development along narrow uplifted zones.

Journal Articles

Ground-state configuration of the $$N=157$$ nucleus $$^{259}$$No

Asai, Masato; Tsukada, Kazuaki; Sakama, Minoru*; Haba, Hiromitsu*; Ichikawa, Takatoshi*; Ishii, Yasuo; Toyoshima, Atsushi; Ishii, Tetsuro; Nishinaka, Ichiro; Nagame, Yuichiro; et al.

Physical Review C, 87(1), p.014332_1 - 014332_6, 2013/01

 Times Cited Count:6 Percentile:44.93(Physics, Nuclear)

The spin-parity and neutron configuration of the ground state of $$^{259}$$No have been identified through $$alpha$$-decay spectroscopy. The $$^{259}$$No is the nucleus with the largest neutron number whose spin-parities and single-particle configurations have ever been identified. The neutron 9/2$$^{+}$$[615] configuration was assigned to the ground state of $$^{259}$$No as well as to the 231.4 keV level in $$^{255}$$Fm. This allowed us to establish energy spacings and order of the neutron single-particle orbitals in such heaviest nuclear region. The appearance of the 9/2$$^{+}$$[615] ground state at $$N$$=157 implies that the order of the neutron orbitals between the $$N$$=152 and 162 deformed shell gaps should change considerably with increasing neutron number.

Journal Articles

Effects of local toroidal field ripple due to test blanket modules for ITER on radial transport of thermal ions

Oyama, Naoyuki; Urano, Hajime; Shinohara, Koji; Honda, Mitsuru; Takizuka, Tomonori; Hayashi, Nobuhiko; Kamada, Yutaka; JT-60 Team

Nuclear Fusion, 52(11), p.114013_1 - 114013_9, 2012/11

 Times Cited Count:4 Percentile:18.45(Physics, Fluids & Plasmas)

Effects of local toroidal field (TF) ripple due to test blanket modules (TBMs) for ITER on radial transport of thermal ions are investigated using fully three-dimensional magnetic field orbit following Monte Carlo (F3D-OFMC) code. The simulation under ITER plasma condition indicates that the additional losses caused by the localized TF ripple due to TBMs linearly increase with number of TBMs. When the amplitude of local TF ripple in one TBM port is increased, on the other hand, the additional losses increase quickly. A comparison of the number of lost particles suggests that a condition with three TBM ports corresponds to 1.7 times of ripple amplitude at one TBM port.

Journal Articles

Core transport properties in JT-60U and JET identity plasmas

Litaudon, X.*; Sakamoto, Yoshiteru; de Vries, P. C.*; Salmi, A.*; Tala, T.*; Angioni, C.*; Benkadda, S.*; Beurskens, M. N. A.*; Bourdelle, C.*; Brix, M.*; et al.

Nuclear Fusion, 51(7), p.073020_1 - 073020_13, 2011/07

 Times Cited Count:8 Percentile:35.77(Physics, Fluids & Plasmas)

A variety of triggering mechanisms and structures of internal transport barrier (ITB) has been observed in various devices or depending on operation scenarios. Thus identity experiments on ITB in JT-60U and JET have been performed to shed light on the physics behind ITBs. Because of their similar size, the dimensionless parameters between both devices are the same. These experiments were performed with near identical magnetic configurations, heating waveforms and normalized quantities such as safety factor, magnetic shear, normalized Larmor radius, normalized collision frequency, beta, temperatures ratio. Similarities of the ITB triggering mechanism and the ITB strength have been observed when a proper match is achieved of the most relevant profiles of the normalized quantities. This paper will report on the detail comparison of transport properties of ITBs obtained in these JET/JT-60U identity experiments.

Journal Articles

Three dimensional atomic image of TlInSe$$_{2}$$ by X-ray fluorescence holography

Mimura, Kojiro*; Hosokawa, Shinya*; Happo, Naohisa*; Hu, W.; Hayashi, Koichi*; Wakita, Kazuki*; Ishii, Hirofumi*; Yoshimura, Masato*; Jeyakanthan, J.*; Mamedov, N.*

e-Journal of Surface Science and Nanotechnology (Internet), 9, p.273 - 276, 2011/07

Journal Articles

Three-dimensional atomic images of TlInSe$$_{2}$$ thermoelectric material obtained by X-ray fluorescence holography

Hosokawa, Shinya*; Happo, Naohisa*; Hayashi, Koichi*; Mimura, Kojiro*; Wakita, Kazuki*; Hu, W.; Ishii, Hirofumi*; Yoshimura, Masato*; Jeyakanthan, J.*; Mamedov, N.*

Japanese Journal of Applied Physics, 50(5), p.05FC06_1 - 05FC06_2, 2011/05

 Times Cited Count:7 Percentile:32.13(Physics, Applied)

JAEA Reports

Conceptual design of the SlimCS fusion DEMO reactor

Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.

JAEA-Research 2010-019, 194 Pages, 2010/08


This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m$$^{2}$$. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.

161 (Records 1-20 displayed on this page)