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Nohara, Tsuyoshi; Uno, Masaoki*; Tsuchiya, Noriyoshi*
Geofluids, 2019, p.6053815_1 - 6053815_16, 2019/08
Times Cited Count：4 Percentile：27.96(Geochemistry & Geophysics)Amphibole-plagioclase thermometry was applied to estimate the temperature of a glassy vein as approximately 700. The results of observations of the rock core revealed that of supercritical fluid flow was microfracture filling with hornblende and plagioclase. The current high permeability was recognized to be microfracture network. A high-angle fracture of chlorite filling in combination with an open fracture was recognized as characteristics of a high-permeability type.
Takase, Kazuyuki; Misawa, Takeharu*
Supercritical-Pressure Light Water Cooled Reactors, p.301 - 319, 2014/12
no abstracts in English
Oyama, Yukio; Ikeda, Yujiro
Hoshasen To Sangyo, (107), p.45 - 51, 2005/09
JAERI and KEK are jointly conducting high intensity proton accelerator project (J-PARC). The outline of the J-PARC project and a design concept of the neutron source facility at J-PARC are described in detail.
Nakamura, Tatsuya; Katagiri, Masaki; Aratono, Yasuyuki; Kanno, Ikuo*; Hishiki, Shigeomi*; Sugiura, Osamu*; Murase, Yasuhiro*
Review of Scientific Instruments, 75(2), p.340 - 344, 2004/02
Times Cited Count：6 Percentile：34.53(Instruments & Instrumentation)We evaluated the neutron-detection characteristics of a proposed cryogenic neutron detector comprising an InSb semiconductor detector and a helium-3 gas converter. The neutron detector was operated at 4.2 K with helium-3 gas filling up to 1.5 atm, at which the density of the helium-3 nucleus corresponds to that at 160 atm at room temperature. The secondary particles generated by the 
He(n,p) T reaction were successfully detected by the InSb detector with a time response of 
80 nsec at all tested gas pressures.
Sono, Hiroki; Yanagisawa, Hiroshi*; Miyoshi, Yoshinori
JAERI-Tech 2003-096, 84 Pages, 2004/01
Prior to the supercritical experiments using a water-reflected core of the TRACY Facility, neutronic characteristics regarding criticality and reactivity of the core system were evaluated. In the analyses, a continuous energy Monte Carlo code, MVP, and a two-dimensional transport code, TWOTRAN, were used together with a nuclear data library, JENDL-3.3. By comparison to the characteristics in the former-used bare core system of TRACY, the water reflector was estimated not to change the kinetic parameter and to reduce the critical solution level by 20 %, the temperature coefficient of reactivity by 610 %, and the void coefficient of reactivity by 18 %, respectively. According to the Nordheim-Fuchs model, the first peak power during a power excursion was evaluated to be 15 % smaller than that in the bare system under the same conditions of fuel and reactivity insertion. The influence of the void feedback effect of reactivity, which is left out of consideration in the model, on the power characteristics will be evaluated from the results of the experiments.
Akiba, Masato; Ishitsuka, Etsuo; Enoeda, Mikio; Nishitani, Takeo; Konishi, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 79(9), p.929 - 934, 2003/09
no abstracts in English
Aso, Tomokazu; Sato, Hiroshi; Kaminaga, Masanori; Hino, Ryutaro; Monde, Masanori*
Proceedings of ICANS-XVI, Volume 2, p.935 - 944, 2003/07
no abstracts in English
Nakajima, Ken
Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 8 Pages, 2002/10
The nuclear characteristics of TRACY, such as the criticality, the 
/
ratio, the peak power, the energy of pulse, and the total energy, have been evaluated using the experimental data. TRACY is a supercritical reactor fueled with low-enriched uranyl nitrate aqueous solution to simulate criticality accidents in a fuel processing facility, such as a spent-fuel reprocessing plant. In this evaluation, the availability of criticality calculation and the models to evaluate the power and energy have been studied.
Guillemet, L.*; Jager, B.*; Haange, R.*; Hamada, Kazuya; Hara, Eiji*; Kalinin, G.*; Kato, Takashi; Millet, F.*; Shatil, N.*
Proceedings of 19th International Cryogenic Engineering Conference (ICEC-19), p.105 - 108, 2002/07
Japan Atomic Energy Research Institute has designed a ITER cryoplant and cryo-distribution in the international collaboration. The ITER cryoplant that will be the largest cryogenic system for the Fusion facility in the world, is designed to be stable in operation despite the pulsed nature of heat deposition in the magnet system. The refrigeration capacity of cryoplant is 48 kW at 4.5 K of refrigeration power and 0.16 kg/s of supercritical helium supply. In the cryoplant, a supercritical helium pump and a cold compressor is applied, based on the successful achievement of cryogenic system for the ITER central solenoid model coil.
Hamada, Kazuya; Koizumi, Norikiyo
Purazuma, Kaku Yugo Gakkai-Shi, 78(7), p.616 - 624, 2002/07
In the Tokamak type fusion reactor design, a forced flow superconducting coil is applied from the viewpoint to high magnetic field, high withstand voltage performance and large electromagnetic force. In the forced flow magnets, it is well known that various electromagnetic phenomena are occurred by zero resistance and diamagnetic effect of superconductor and complicated structure of cable in conduit conductor (CICC). In the R&D of CICC, the study of hysteresis losses and coupling losses CICC have a lot of progress. For example, using the optimization of filament arrangement in superconducting strand and control of contact resistance of strand, ITER model coil project have a large achievement.
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Kato, Takashi; Nakajima, Hideo; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Sugimoto, Makoto; Nunoya, Yoshihiko; Koizumi, Norikiyo; Matsui, Kunihiro; Oshikiri, Masayuki*; et al.
Teion Kogaku, 36(6), p.315 - 323, 2001/06
no abstracts in English
Sugimoto, Makoto
JAERI-Research 2000-069, 134 Pages, 2001/03
JAERI-Research-2000-069.pdf:7.46MB
no abstracts in English
Kato, Takashi
Tabo Kikai, 28(9), p.536 - 545, 2000/09
no abstracts in English
Sugimoto, Makoto; Kato, Takashi; Isono, Takaaki; Yoshida, Kiyoshi; Tsuji, Hiroshi
Cryogenics, 39(4), p.323 - 330, 1999/00
Times Cited Count：4 Percentile：23.25(Thermodynamics)no abstracts in English
Nakajima, Ken; ;
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 3, p.1286 - 1292, 1999/00
no abstracts in English
Sugimoto, Makoto; Isono, Takaaki; Tsuji, Hiroshi; Yoshida, Kiyoshi; ; Hamajima, Takataro*; Sato, Takashi*; Shinoda, K.*
Cryogenics, 38(10), p.989 - 994, 1998/00
Times Cited Count：4 Percentile：23.46(Thermodynamics)no abstracts in English
Kawano, Katsumi; Kato, Takashi; Hamada, Kazuya; Shimba, Toru*; Tsuji, Hiroshi; ; ; ;
Proceedings of 17th International Cryogenic Engineering Conference (ICEC17), p.255 - 258, 1998/00
no abstracts in English
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
Takahashi, Yoshikazu; Oshikiri, Masayuki*; Kawano, Katsumi; Hanawa, Hiromi*; Imahashi, Koichi*; Seki, Shuichi*; Otsu, K.*; Wakabayashi, Hiroshi*; Takano, Katsutoshi*; Uno, Yasuhiro*; et al.
Teion Kogaku, 33(5), p.323 - 333, 1998/00
no abstracts in English
