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Nabeshima, Kunihiko
JAERI 1342, 119 Pages, 2001/03
no abstracts in English
Nomura, Toshibumi
Hoken Butsuri, 35(1), p.127 - 135, 2000/03
no abstracts in English
Nabeshima, Kunihiko; Suzudo, Tomoaki; Takizawa, Hiroshi*; Ono, Tomio*; Kudo, Kazuhiko*
Proceedings of International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies (NPIC&HMIT 2000) (CD-ROM), 9 Pages, 2000/00
no abstracts in English
; ; 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.
Nabeshima, Kunihiko; Suzuki, Katsuo; Inoue, K.*; *
Engineering Benefits from Neural Networks, p.257 - 260, 1998/00
no abstracts in English
Nabeshima, Kunihiko; Nose, Shoichi*; *; Suzuki, Katsuo
JAERI-Research 96-051, 46 Pages, 1996/10
JAERI-Research-96-051.pdf:1.51MB
no abstracts in English
; Tanabe, Fumiya; *
Keisoku Jido Seigyo Gakkai Rombunshu, 32(4), p.567 - 576, 1996/04
no abstracts in English
Nabeshima, Kunihiko; Suzuki, Katsuo; Shinohara, Yoshikuni*; E.Tuerkcan*
JAERI-Research 95-076, 33 Pages, 1995/11
JAERI-Research-95-076.pdf:1.03MB
no abstracts in English
Nabeshima, Kunihiko
Tokei Suri Kenkyujo Kyodo Kenkyu Ripoto 68, 0, p.43 - 52, 1995/03
no abstracts in English
Nabeshima, Kunihiko; Suzuki, Katsuo; E.Tuerkcan*; Oe.Ciftcioglu*
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1551 - 1556, 1995/00
no abstracts in English
;
Hoken Butsuri, 27, p.41 - 47, 1992/00
no abstracts in English
Yokobayashi, Masao;
Nippon Genshiryoku Gakkai-Shi, 33(7), p.695 - 702, 1991/07
no abstracts in English
*; ; ; ; Fukami, Akihiro*; *; Igawa, Kenichi*
PNC-TN9410 91-175, 52 Pages, 1991/05
An acoustic detection method is one of the FBR reactor core malfunction detection methods, and is regarded as being promising. In this study, the preliminary experiment of boiling detection by acoustic method was conducted at JOYO to measure the acoustic signal level and to investigate the applicability of the acoustic method. The experiment was performed on June 13 and 14, 1990 during the 8th periodic inspection of JOYO. The results obtained though the experiment are as follows: (1)Sodium bubbling (boiling) induced by the electric heater was detected as the fluctuation of temperature single of the thermocouple attached to surface of the electric heater. (2)Bubbling single of the acoustic detector could not be identified cleary because of the high background noise caused by the primary main pump vibration, sodium flow in the reacter vessel and the electric supply in the containment vessel. (3)The correlation between the signal of the acoustic detector or the fluctuation of temperature signal of the thermocouple and the flow rate of the primary loops was not ascertained. It became clear through this study that the validity of the reactor core malfunction detction by acoustic method depend on the peculiar noise level in the reactor vessel, and the reduction of noise is the subject for a future study.
Yokobayashi, Masao; Matsumoto, Kiyoshi; Murayama, Yoji; Kaminaga, Masanori; Kosaka, Atsuo
JAERI-M 90-207, 26 Pages, 1990/11
no abstracts in English
; Yokobayashi, Masao
JAERI-M 89-184, 157 Pages, 1989/11
no abstracts in English
JAERI-M 89-183, 13 Pages, 1989/11
no abstracts in English
; Yokobayashi, Masao; Matsumoto, Kiyoshi; Kosaka, Atsuo
Journal of Nuclear Science and Technology, 26(11), p.1002 - 1012, 1989/11
no abstracts in English
*; *; *; Fujiki, Kazuo; Kosaka, Atsuo; *
Tech. Rep. Inst. At. Energy,Kyoto Univ., 211, p.1 - 57, 1989/05
no abstracts in English
