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Yang, M.*; Kamikubota, Norihiko*; Sato, Kenichi*; Kikuzawa, Nobuhiro; Tajima, Yuto*
Proceedings of 18th International Conference on Accelerator and Large Experimental Physics Control Systems (ICALEPCS 2021) (Internet), p.927 - 930, 2022/02
Since 2006, the Japan Proton Accelerator Research Complex (J-PARC) timing system has been operated successfully. However, there were some unexpected trigger-failure events, typically missing trigger events, during the operation over 15 years. When a trigger-failure event occurred, it was often tough to find the one with the fault among many suspected modules. To solve the problem more easily, a unique device, triggered scaler, was developed for reading back accelerator signals. The performance of the module has been evaluated in 2018. In 2021, we measured and observed an LLRF signal as the first signal of the read-back system for beam operation. After firmware upgrades of the module, some customized timing read-back systems were developed, and successfully demonstrated as coping strategies for past trigger-failure events. In addition, a future plan to apply the read-back system to other facilities is discussed. More details are given in the paper.
Yang, M.*; Kamikubota, Norihiko*; Tajima, Yuto*; Sato, Kenichi*; Kikuzawa, Nobuhiro
Proceedings of 22nd Virtual IEEE Real Time Conference (Internet), 5 Pages, 2020/10
During the operation of J-PARC timing system since 2006, there were a few unexpected trigger-failure events occurred. It was difficult to find the faulty module among many suspicious modules. In order to find such a module easily, a Yokogawa PLC-type triggered scaler module was developed. It can accept the start of J-PARC Main Ring (MR) slow cycle (2.48s/5.2s) signal and the start of rapid cycle (25Hz) signal, which are generated by J-PARC timing system. A scaler in the module counts number of trigger pulses during the J-PARC slow cycle and stores counts in an array. In 2018, the module was tested successfully and the results showed the expected performance. The details of the module and two associated applications will be described in the paper.
Taba, Ryo*; Takemura, Fumiaki*; Tansuriyavong, S.*; Kawabata, Kuniaki; Sagara, Shinichi*; Ogasawara, Kei*
Proceedings of 21st International Symposium on Artificial Life and Robotics (AROB 21st 2016) and 1st International Symposium on BioComplexity (ISBC-1) (Internet), p.395 - 399, 2016/01
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count：62 Percentile：96.4(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Oka, Kiyoshi; Shibanuma, Kiyoshi
Advanced Robotics, 16(6), p.493 - 496, 2002/12
Times Cited Count：8 Percentile：39.11(Robotics)no abstracts in English
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.
Research Committee for Fusion Reactor; Research Committee for Fusion Materials
JAERI-Review 2002-008, 79 Pages, 2002/03
JAERI-Review-2002-008.pdf:9.92MB
Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.
Terada, Hiroaki; Ueda, Hiromasa*; Wang, Z.*
Atmospheric Environment, 36(3), p.503 - 509, 2002/01
Times Cited Count：48 Percentile：70.24(Environmental Sciences)Acid rain and its neutralization by yellow-sand in East Asia was investigated numerically by an Air Quality Prediction Modeling System (AQPMS). AQPMS consists of advection, diffusion, dry and wet deposition, gas- and liquid-phase chemistry. A new deflation module of the yellow-sand was designed to provide explicit information on the dust loading, and linked to the AQPMS. For model validation, the predicted pH values and sulfate- and nitrate-ion levels of precipitation, together with the surface concentrations of gaseous pollutants, were compared with measured values at atmospheric monitoring stations, and a reasonable agreement was obtained. Firstly, trend of the acid rain in East Asia due to the rapid increase of Chinese pollutants emission was investigated, and a remarkably rapid increase of acid rain area was predicted in the period from 1985 to 1995. Secondly, the simulation results of April 1995 exhibited a strong neutralization of the precipitation by the yellow-sand.
Enoeda, Mikio; Kuroda, Toshimasa*; Moriyama, Koichi*; Ohara, Yoshihiro
Journal of Nuclear Science and Technology, 38(11), p.921 - 929, 2001/11
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)Test module testing in ITER is one of the most important mile-stone for development of the DEMO blanket. In the design of test modules in ITER, it is very important to show that test modules do not cause additional safety concern to ITER. This work has been performed for the evaluation of the substantial safety of Test Module of Water Cooled Solid Blanket, which is the current candidate blanket for the DEMO blanket in Japan. Major issues of the evaluation were establishment of post accident cooling in TM, hydrogen gas generation by Be-steam reaction, and pressure increase and spilled water amount by Loss of Coolant Accident (LOCA) event. The evaluation was performed to derive the upper bound of consequences in significant events, of which scenario can be assumed by the similarity of the safety analysis of Shielding Blanket.
Shibata, Taiju; Ishihara, Masahiro; Takahashi, Tsuneo*; Motohashi, Yoshinobu*; Hayashi, Kimio
JAERI-Research 2001-024, 24 Pages, 2001/03
JAERI-Research-2001-024.pdf:6.25MB
no abstracts in English
Yan, X.; Shiozawa, Shusaku; Kunitomi, Kazuhiko; Muto, Yasushi; Miyamoto, Yoshiaki; Katanishi, Shoji
Proceedings of 8th International Conference on Nuclear Engineering (ICONE-8) (CD-ROM), p.8 - 0, 2000/00
no abstracts in English
Miura, H.*; Sato, Satoshi; Enoeda, Mikio; Kuroda, Toshimasa*; Takatsu, Hideyuki; Kawamura, Yoshinori; Tanaka, Satoru*
JAERI-Tech 97-051, 51 Pages, 1997/10
no abstracts in English
Araki, Masanori; Sato, Kazuyoshi; ; Akiba, Masato
Fusion Technology, 30(3), p.674 - 679, 1996/12
no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Seki, Yasushi; *
J. Fusion Eng. Des., 30(3), p.1129 - 1133, 1996/12
no abstracts in English
Nakahira, Masataka; Kurasawa, Toshimasa; Sato, Satoshi; Furuya, Kazuyuki; *; Hashimoto, T.*; Kuroda, Toshimasa*; Takatsu, Hideyuki
JAERI-Tech 95-035, 20 Pages, 1995/07
no abstracts in English
Sato, Satoshi; Takatsu, Hideyuki; Kurasawa, Toshimasa; Hashimoto, T.*; Koizumi, Koichi; *; *; *; Tada, Eisuke; Nakahira, Masataka; et al.
JAERI-Tech 95-019, 129 Pages, 1995/03
no abstracts in English
*; *; Araya, Fumimasa;
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.469 - 474, 1995/00
no abstracts in English
Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; *; H.Werner*
Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Araya, Fumimasa; *; *; ;
Proc. of the Joint Int. Conf. on Mathematical Methods and Supercomputing in Nuclear Applications,Vol. 1, p.466 - 476, 1993/00
no abstracts in English
