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Oi, Motoki; Sakai, Kenji; Watanabe, Akihiko; Akutsu, Atsushi; Meigo, Shinichiro; Takada, Hiroshi
JPS Conference Proceedings (Internet), 8, p.036007_1 - 036007_5, 2015/09
This paper reports on upgrading of the monitor and operation (MO) system for a general control system (GCS) of the Materials and Life science experimental Facility (MLF) at J-PARC. The MLF-GCS consists of programmable logic controllers (PLCs), operator interfaces (OPIs) for integral control and interlock systems, shared servers, and so on. It is controlling various components of the pulsed spallation neutron source such as a mercury target and hydrogen moderators. The MO system is used for monitoring, alarm notification and remote control from the MLF control room. The GCS has been working well as expected, but current MO system which consists of the OPIs and data servers based on iFix has some problems in view of sustainable maintenance because of its poor flexibility of supported OS and software version compatibility. To overcome the problems, we upgraded the MO system to be operated using the framework of EPICS, the OPI of Control System Studio (CSS) and the server software of Postgre SQL. This improves versatility of the MO system, enabling to run on various platforms such as Windows, Linux and Mac OS. At first, we made a prototype MO system, which processed 100 points of data and 5 operation screens and verified that the MO system functions correctly. Then we made full spec MO system which processes the data point of 7000 and operation screens of 130. It was operated in parallel with the current system to evaluate its performance with real data such as data transmission speed from PLCs, control functions from OPI, storage capability of servers and long-term reliability. As results, the new MO system achieved the communication speed of 2 Hz and its operability compatible to the current system. Now, we are operating and debugging it in comparison with the current system during the operating period as a preparation for the system replacement at the end of 2014.
Kurihara, Kenichi; Yonekawa, Izuru; Kawamata, Yoichi; Sueoka, Michiharu; Hosoyama, Hiroki*; Sakata, Shinya; Oshima, Takayuki; Sato, Minoru; Kiyono, Kimihiro; Ozeki, Takahisa
Fusion Engineering and Design, 81(15-17), p.1729 - 1734, 2006/07
Times Cited Count:13 Percentile:65.83(Nuclear Science & Technology)A large tokamak fusion device JT-60 is expected to explore more advanced tokamak discharge scenario towards the ITER and a future power reactor. We believe the following experimental issues are expected to be solved in JT-60. To clarify how to keep a steady-state plasma with high performance, and how to avoid plasma instabilities almost completely. By stimulus of this motivation, several essential development and modifications of plasma control and data acquisition systems have been performed in JT-60. In this report, we discuss the developments to improve the JT-60 plasma control and data acquisition systems. In addition, a future plasma control and data acquisition systems leading to a standard design for a power reactor is envisaged on the basis of the 20-year plasma operation experiences.
Takahashi, Hiroki; Sakaki, Hironao; Sako, Hiroyuki; Yoshikawa, Hiroshi; Kato, Yuko*; Sugimoto, Makoto*; Kawase, Masato*
Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.233 - 235, 2004/08
3GeVRCS send the beam of a different parameter to both the institutions of MLF and 50GeVMR. Therefore, 3GeVRCS Control System is required to supervise by distinguishing the beam for every institution correctly. Moreover, since a parameter change is made during continuation operation, without suspending an accelerator, it is required that the beam loss by operation should be reduced as much as possible. This report shows the examination and design situation of 3GeVRCS control system that aim at these realizations.
Okano, Fuminori; Suzuki, Sadaaki
JAERI-Tech 2003-059, 57 Pages, 2003/06
no abstracts in English
Ozaki, M.*; Hanashima, Susumu
Dai-15-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, p.82 - 85, 2003/03
no abstracts in English
Yoshimi, Takashi*; Kakudate, Satoshi; Tada, Eisuke; Tsuji, Koichi*; Miyagawa, Shinichi*; Kubo, Tomomi*
Nihon Robotto Gakkai-Shi, 19(6), p.766 - 774, 2001/09
no abstracts in English
; Tani, Satoshi; Yoshikawa, Shinji
PNC TN9410 98-023, 29 Pages, 1998/03
Many research activities are conducted to enhance cost performance and safety of nuclear power plants operation and maintenance. Concept of autonomous operating system to equal the role of operators and of maintenance personnel with artificial intelligence and autonomous robots has been developed. An intellectual maintenance management system has been developed to be equipped with decision making functions of maintenance personnel. The intellectual maintenance management system is in charge of maintenance function of an autonomous plant, which consists of plant-wide monitoring, evaluation of component integrity, and scheduling of maintenance activities. In other words, this system should be equipped with preventive maintenance and corrective maintenance functions those are currently loaded on personnel. In this report, we discussed condition monitoring maintenance in the preventive maintenance. We also reported a sensor validation system development for machinery condition monitoring and diagnosis. We adopted distributed and cooperative system construction technique, which is expected recently in applications to large-scale plants. This system has inter-agent communication function for signal transmission and reception among distributed physics models of machineries. The system has been constructed for water / steam system of the LMFBR power plant. The system has been validated to be capable of cooperative sensor validation by the distributed set of agents, with quantitative indication of sensor deviation based on a newly developed fuzzy algorithm with inter-agent cooperation. The derived reference parameter value from the inter-agent evaluations also stands for the alternative measurment to the malfunctioned sensor.
; Murayama, Yoji; Takayanagi, Masaji; Ara, Katsuyuki
IAEA-TECDOC-973, 0, p.113 - 120, 1997/10
no abstracts in English
Hanashima, Susumu
Proc. of 11th Symp. on Accelerator Sci. and Technol., p.519 - 521, 1997/00
no abstracts in English
; ; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 96-101, 40 Pages, 1996/04
Since it is desired to enhance availability and safety of nuclear power plants operation and maintenance by removing human factor, there are many researches and developments for intelligent operation or diagnosis using artificial intelligennce (AI) technique. We have been developing an autonomous operation and maintenance system for nuclear power plants by substituting AI's and intelligent robots. It is indispensable to use various and large scale knowledge relative to plant design, operation, and maintenance, that is, whole life cycle data of the plant for the autonomous nuclear power plant. These knowledge must be given to AI system or intelligent robots adequately and opportunely. Moreover, it is necessaly to insure real time operation using the large scale knowledge base for plant control and diagnosis performance. We have been studying on the large scale and real time knowledge base system for autonomous plant. In the report, we would like to present the basic concept and expecting performance of the knowledge base for autonomous plant, especialy, autonomous control and diagnosis system.
Hanashima, Susumu
Dai-9-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, 0, p.57 - 59, 1996/00
no abstracts in English
Ugolini; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 95-253, 13 Pages, 1995/10
This report presents the implementation of the a model reference adaptive control system based on the artificial neural network technique (MRAC) in a fast breeder reactor (FBR) building block type (BBT) simulator representing the Monju prototype reactor. The purpose of this report is to improve the control of the outlet steam temperature of the three evaporators of the Monju prototype reactor. The connection between the MRAC system and the BBT simulator is achieved through an external shared memory accessible by both systems. The MRAC system calculates the demand for the position of the feedwater valve replacing the signal of a PID controller collocated inside the heat transport system model of the Monju prototype reactor. Two series of simulation tests havc been performed, one with one loop connected to the MRAC system (leaving the remaining two connected to the original PID controller), and the other with three loops connected to the MRAC system. In both simulation tests the MRAC system performed better than the PID controller, keeping the outlet steam temperature of the evaporators closer to the required set point value through all the transients.
Hanashima, Susumu
JAERI-Conf 95-021, 0, p.436 - 438, 1995/10
no abstracts in English
Yamanishi, Toshihiko; Okuno, Kenji
JAERI-M 93-162, 23 Pages, 1993/09
no abstracts in English
Hanashima, Susumu; ; *; *; *; *
Proc. of the 9th Symp. on Accelerator Science and Technology, p.86 - 88, 1993/00
no abstracts in English
Hanashima, Susumu; ; *; *; *; *
Transputer/Occam Japan 5, p.69 - 81, 1993/00
no abstracts in English
Hanashima, Susumu; ; Horie, Katsuzo; Tsukihashi, Yoshihiro
KEK-PROC-92-15, p.333 - 335, 1992/12
no abstracts in English
Kurihara, Kenichi; *; Nakamura, Yukiharu; Kimura, Toyoaki
JAERI-M 89-126, 387 Pages, 1989/09
no abstracts in English
Kawarasaki, Yuki; Sugimoto, Masayoshi
Proceedings of the 7th Symposium on Accelerator Science and Technology, p.262 - 263, 1989/00
no abstracts in English