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Journal Articles

High-temperature gaseous reaction of cesium with siliceous thermal insulation; The Potential implication to the provenance of enigmatic Fukushima cesium-bearing material

Rizaal, M.; Nakajima, Kunihisa; Saito, Takumi*; Osaka, Masahiko; Okamoto, Koji*

ACS Omega (Internet), 7(33), p.29326 - 29336, 2022/08

 Times Cited Count:2 Percentile:29.84(Chemistry, Multidisciplinary)

Journal Articles

Investigation of high-temperature chemical interaction of calcium silicate insulation and cesium hydroxide

Rizaal, M.; Nakajima, Kunihisa; Saito, Takumi*; Osaka, Masahiko; Okamoto, Koji*

Journal of Nuclear Science and Technology, 57(9), p.1062 - 1073, 2020/09

 Times Cited Count:8 Percentile:71.58(Nuclear Science & Technology)

The interaction of cesium hydroxide and a calcium silicate insulation material was experimentally investigated at high temperature conditions. A thermogravimetry equipped with differential thermal analysis was used to analyze thermal events in the samples of mixed calcium silicate and cesium hydroxide under Ar-5%H$$_{2}$$ and Ar-4%H$$_{2}$$-20%H$$_{2}$$0 with maximum temperature of 1100$$^{circ}$$C. Prior being mixed with cesium hydroxide, a part of calcium silicate was pretreated at high temperature to evaluate the effect of possible structural changes of this material due to a preceding thermal history and also the sake of thermodynamic evaluation to those available ones. Based upon the initial condition (preliminary heat treatment) of calcium silicate, it was found that if the original material consisted of xonotlite (Ca$$_{6}$$Si$$_{6}$$0$$_{17}$$(0H)$$_{2}$$), the endothermic reaction with cesium hydroxide occurred over the temperature range 575-730$$^{circ}$$C meanwhile if the crystal phase of original material was changed to wollastonite (CaSi0$$_{3}$$), the interaction occurred over temperature range 700-1100$$^{circ}$$C. Furthermore, the X-ray diffraction analyses have indicated on both type of pretreated calsils that regardless of Ar-5%H$$_{2}$$ and Ar-4%H$$_{2}$$-20%H$$_{2}$$0 atmosphere, cesium aluminum silicate, CsAlSi0$$_{4}$$ was formed with aluminum in the samples as an impurity or adduct.

Journal Articles

1 MeV, ampere class accelerator R&D for ITER

Inoue, Takashi; Kashiwagi, Mieko; Taniguchi, Masaki; Dairaku, Masayuki; Hanada, Masaya; Watanabe, Kazuhiro; Sakamoto, Keishi

Nuclear Fusion, 46(6), p.S379 - S385, 2006/06

 Times Cited Count:35 Percentile:74.54(Physics, Fluids & Plasmas)

The JAERI MeV accelerator has been designed extrapolating vacuum insulation design guidelines (the clump theory and Paschen law) to Mega Volt and long vacuum gap. Reduction of electric field concentration at triple junction by a large stress ring was effective to prevent flashover along insulator surface. By the vacuum insulation technology above, the accelerator sustained 1 MV for 8,500 s continuously. Strong enhancement of negative ion surface production has been attained by stopping vacuum leaks due to SF$$_{6}$$ permeation through Viton O rings and a damage of port by backstream ions, followed by increase of the H$$^{-}$$ ion current density without saturation. Operating the KAMABOKO source with high power arc discharge ($$leq$$ 40 kW), H$$^{-}$$ ion beams of 146 A/m$$^{2}$$ (total ion current: 0.2 A) have been obtained stably at the beam energy of 836 keV (pulse length: $$geq$$ 0.2 s). Bremsstrahlung generation in the accelerator is also estimated from EGS4 analysis, and then discussion on the breakdown possibility follows.

Journal Articles

Design study of a neutral beam injector for fusion DEMO plant at JAERI

Inoue, Takashi; Hanada, Masaya; Kashiwagi, Mieko; Nishio, Satoshi; Sakamoto, Keishi; Sato, Masayasu; Taniguchi, Masaki; Tobita, Kenji; Watanabe, Kazuhiro; DEMO Plant Design Team

Fusion Engineering and Design, 81(8-14), p.1291 - 1297, 2006/02

 Times Cited Count:11 Percentile:60.27(Nuclear Science & Technology)

Requirement and technical issues of the neutral beam inejctor (NBI) is discussed for fusion DEMO plant. The NBI for the fusion DEMO plant should be high efficiency, high energy and high reliability with long life. From the view point of high efficiency, use of conventional electrostatic accelerator is realistic. Due to operation under radiation environment, vacuum insulation is essential in the accelerator. According to the insulation design guideline, it was clarified that the beam energy of 1.5$$sim$$2 MeV is possible in the accelerator. Development of filamentless, and cesium free ion source is required, based on the existing high current/high current density negative ion production technology. The gas neutralization is not applicable due to its low efficiency (60%). R&D on an advanced neutralization scheme such as plasma neutralization (efficiency: $$>$$80%) is required. Recently, development of cw high power semiconductor laser is in progress. The paper shows a conceptual design of a high efficiency laser neutralizer utilizing the new semiconductor laser array.

Journal Articles

R&D on a high energy accelerator and a large negative ion source for ITER

Inoue, Takashi; Taniguchi, Masaki; Morishita, Takatoshi; Dairaku, Masayuki; Hanada, Masaya; Imai, Tsuyoshi*; Kashiwagi, Mieko; Sakamoto, Keishi; Seki, Takayoshi*; Watanabe, Kazuhiro

Nuclear Fusion, 45(8), p.790 - 795, 2005/08

The R&D of a 1 MeV accelerator and a large negative ion source have been carried out at JAERI. The paper presents following progress as a step toward ITER NB system. (1) Accelerator R&D: According to success in improvement of voltage holding capability, the acceleration test of H$$^{-}$$ ions up to 1 MeV class energy is in progress. H$$^{-}$$ ion beams of 1 MeV, 100 mA class have been generated with a substantial beam current density (100 A/m$$^{2}$$), and the current density is still increasing by the ion source tuning. (2) Large ion source R&D: One of major causes that limited the NB injection performance was spatial unifomity of negative ion production in existing negative-ion based NB systems. The present study revealed that the negative ions produced in the extraction region of the source were locally destructed by fast electrons leaking through magnetic filter. Some countermeasures and their test results are also described.

Journal Articles

R&D on a high energy accelerator and a large negative ion source for ITER

Inoue, Takashi; Taniguchi, Masaki; Morishita, Takatoshi; Dairaku, Masayuki; Hanada, Masaya; Imai, Tsuyoshi*; Kashiwagi, Mieko; Sakamoto, Keishi; Seki, Takayoshi*; Watanabe, Kazuhiro

Nuclear Fusion, 45(8), p.790 - 795, 2005/08

 Times Cited Count:23 Percentile:59.63(Physics, Fluids & Plasmas)

The R&D of a 1 MeV accelerator and a large negative ion source has been carried out at JAERI for the ITER NB system. The R&D is in progress at present toward: (1) 1 MeV acceleration of H$$^{-}$$ ion beams at the ITER relevant current density of 200 A/m$$^{2}$$, and (2) improvement of uniform negative ion production over wide extraction area in large negative ion sources. Recently, H$$^{-}$$ ion beams of 1 MeV, 140 mA level have been generated with a substantial beam current density (100 A/m$$^{2}$$). In the uniformity study, it has been clarified that electron temperature in the ion extraction region is locally high ($$>$$ 1 eV), which resulted in destruction of negative ions at a high reaction rate. Interception of fast electrons leaking through a transverse magnetic field called "magnetic filter" has been found effective to lower the local electron temperature, followed by an improvement of negative ion beam profile.

JAEA Reports

R&D on high power negative ion sources and accelerators for a neutral beam injector

Inoue, Takashi

JAERI-Research 2005-006, 87 Pages, 2005/03

JAERI-Research-2005-006.pdf:10.53MB

Negative ion sources and accelerators have been developed toward the ITER neutral beam injector (NBI). According to an analysis of negative ion surface production, the "KAMABOKO" ion source has been developed maximizing its volume/surface ratio, for fast electron confinement followed by enhancement of atomic density. An "external filter" is equipped in the source, to suppress ion destruction by the fast electrons with efficient diffusion of the atoms to ion extraction region. H$$^{-}$$ ions of 300 A/m$$^{2}$$ was extracted at the pressure of 0.3 Pa. For the accelerator, vacuum insulation technology has been developed since insulation gas such as SF$$_{6}$$ is not applicable under radiation environment. Considering pressure in the accelerator (0.02$$sim$$0.2 Pa), insulation guideline has been developed for both vacuum arc and glow discharges. Reduction of electric field stress at triple junction was effective to prevent flashover along insulator surface. H$$^{-}$$ ion beams of 900 keV and 80 A/m$$^{2}$$ (total ion current: 0.11 A) were obtained for several hundred shots.

JAEA Reports

Development of the fabrication technology for the superconducting coils in the ITER magnet system and its achievements

Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi; Endo, Sakaru*; Kikuchi, Kenichi*; Kubo, Yoshio*; Aoki, Nobuo*; Yamada, Yuichi*; Osaki, Osamu*; Sasaki, Takashi*; et al.

JAERI-Tech 2002-027, 23 Pages, 2002/03

JAERI-Tech-2002-027.pdf:2.94MB

The Engineering Design Activities (EDA) for the International Thermonuclear Experimental Reactor (ITER) was performed under the collaboration of Japan, EU, Russia and the US. The EDA was successfully completed in July 2001, in which the development of fabrication technology for advanced components, such as superconducting coils, was conducted. The ITER magnet system consists of Toroidal Field coils, a Central Solenoid (CS), Poloidal Field coils and Correction coils. The construction of these coils requires advanced technologies that fairly exceeded those available at the start of the EDA. Therefore, CS Model Coil and TF Model Coil projects were implemented. To fabricate the CS Model Coil, the fabrication technologies for high performance strand, large cable, winding, heat treatment, joint and insulation are indispensable. This report describes the above detailed fabrication technologies successfully developed in the CS Model Coil Project.

Journal Articles

ITER R&D: Auxiliary systems; Neutral beam heating and current drive system

Inoue, Takashi; Hemsworth, R. S.*; Kulygin, V.*; Okumura, Yoshikazu

Fusion Engineering and Design, 55(2-3), p.291 - 301, 2001/07

 Times Cited Count:25 Percentile:84.32(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutral beams for the International Thermonuclear Experimental Reactor

Inoue, Takashi; Di Pietro, E.*; Mondino, P. L.*; Bayetti, P.*; Hemsworth, R. S.*; Massmann, P.*; Fujiwara, Yukio; Hanada, Masaya; Miyamoto, Kenji; Okumura, Yoshikazu; et al.

Review of Scientific Instruments, 71(2), p.744 - 746, 2000/02

 Times Cited Count:17 Percentile:67.92(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Experimental study on the influence of radiation on high-voltage insulation gases

Fujiwara, Yukio; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Ohara, Yoshihiro; Okumura, Yoshikazu; Watanabe, Kazuhiro

JAERI-Research 99-071, p.33 - 0, 1999/12

JAERI-Research-99-071.pdf:1.18MB

no abstracts in English

Journal Articles

Development of silicon nitride fiber from Si-containing polymer by radiation curing and its application

*; Seguchi, Tadao; *

Radiation Physics and Chemistry, 54(6), p.575 - 581, 1999/00

 Times Cited Count:26 Percentile:85.59(Chemistry, Physical)

no abstracts in English

JAEA Reports

Durability of alumina electrical insulation films by plasma spraying coating method under repeated impact loads

Kanari, Moriyasu*; Abe, Tetsuya; Enoeda, Mikio; *; *; Shimizu, Katsusuke*; *; Takatsu, Hideyuki

JAERI-Research 98-029, 23 Pages, 1998/06

JAERI-Research-98-029.pdf:2.51MB

no abstracts in English

Journal Articles

Electrical insulation design and monitoring of the ITER magnet system

Yoshida, Kiyoshi; *; R.Gallix*; S.Sadakov*; R.Vieira*; J.Stoner*; C.Sborchia*

Fusion Technology 1998, 1, p.807 - 810, 1998/00

no abstracts in English

Journal Articles

Radiation analysis of the ITER neutral beam system

Inoue, Takashi; Shibata, Keiichiro*; E.DiPietro*; Fujiwara, Yukio; R.S.Hemsworth*; E.Hodgson*; Iida, Hiromasa; A.Krylov*; P.L.Mondino*; Okumura, Yoshikazu; et al.

Fusion Technology 1998, 1, p.411 - 414, 1998/00

no abstracts in English

Journal Articles

Development of standard components for remote handling

*; Kakudate, Satoshi; Nakahira, Masataka; *

J. Robot. Mechatron., 10(2), p.133 - 138, 1998/00

no abstracts in English

Journal Articles

Mechanical strength of alumina ceramics in low temperatures

Sugimoto, Makoto; Takano, Katsutoshi*; Tsuji, Hiroshi; Abe, Kazuhiko*; *; *

Teion Kogaku, 33(11), p.716 - 723, 1998/00

no abstracts in English

Journal Articles

Development of remote handling tools and equipment

Nakahira, Masataka; Oka, Kiyoshi; *; *; *; Oda, Yasushi*; Kajiura, Soji*; Yamazaki, Seiichiro*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.54 - 68, 1997/01

no abstracts in English

Journal Articles

Radiation induced conductivity and voltage holding characterisics of insulation gas for the ITER-NBI

Fujiwara, Yukio; Hanada, Masaya; Inoue, Takashi; Miyamoto, Kenji; Miyamoto, Naoki*; Ohara, Yoshihiro; Okumura, Yoshikazu; Watanabe, Kazuhiro

Proc. of Joint Meeting of 8th Int. Symp. on the Production and Neutralization of Negative Ions & Beams, p.205 - 215, 1997/00

no abstracts in English

Journal Articles

Electrical insulation and conduction coating for fusion experimental devices

Onozuka, Masanori*; Tsujimura, Seiji*; Toyoda, Masahiko*; Inoue, Masahiko*; Abe, Tetsuya; Murakami, Yoshio

Fusion Technology, 29(1), p.73 - 82, 1996/01

 Times Cited Count:9 Percentile:62.07(Nuclear Science & Technology)

no abstracts in English

37 (Records 1-20 displayed on this page)