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Nishimura, Akihiko; Takenaka, Yusuke*; Furuyama, Takehiro*; Shimomura, Takuya; Terada, Takaya; Daido, Hiroyuki
Journal of Laser Micro/Nanoengineering, 9(3), p.221 - 224, 2014/11
Times Cited Count：0 Percentile：0(Nanoscience & Nanotechnology)Heat resistant FBG sensors were developed by femtosecond laser processing to apply them to high temperature operated piping system of nuclear power plants. The FBG sensor was installed on the surface of a steel blade and a vibration test was conducted to detect the resonant vibration frequency of the vibrating blade. The FBG sensor had the heatproof performance at 600
C. A frequency stabilized sensing system using a tunable laser was tested for structural health monitoring in daily operation of nuclear power plants. The FBG sensor was installed on the surface of a steel blade for vibration induced strain measurements. Welding, brazing, soldering and noble metal powder adhesive were discussed for molding the FBG sensors.
Nishi, Hiroshi
Fusion Engineering and Design, 81(1-7), p.269 - 274, 2006/02
Times Cited Count：4 Percentile：30.68(Nuclear Science & Technology)Tensile strength of the diffusion bonded joint was as large as that of Alumina dispersion-strengthened copper (DS Cu), however, the Charpy absorbed energy of the joint was considerably lower than that of DS Cu. Instrumented Charpy impact test and slow-bend Charpy test of diffusion bonded joints were performed to clarify the degradation of Charpy absorbed energy. Elasto-plastic analyses were also carried out in order to study the deformation behavior of the tensile and V-notched specimens for joints. As the results, the fracture behaviors of the impact and slow-bend tests were almost the same. Elasto-plastic analyses showed that the maximum strain occurred at the DS Cu apart from the interface for tensile specimen, however, the strain concentrated at the DS Cu near the interface for the notched specimen. This strain concentration arose from the mechanical heterogeneity between stainless steel and DS Cu in the bonded zone and attributed to the degradation of the absorbed energy of the joints.
Fukuda, Takeshi; Oikawa, Toshihiro; Takeji, Satoru; Isayama, Akihiko; Kawano, Yasunori; Neyatani, Yuzuru; Nagashima, Akira; Nishitani, Takeo; Konoshima, Shigeru; Tamai, Hiroshi; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.357 - 367, 2002/09
Times Cited Count：7 Percentile：44.35(Nuclear Science & Technology)no abstracts in English
Onizawa, Kunio; Van Walle, E.*; Pavirich, W.*; Nanstad, R.*
NUREG/CR-6777, 81 Pages, 2002/08
no abstracts in English
Yamagishi, Hideshi; Soyama, Kazuhiko; Kakuta, Tsunemi; Ochiai, Masaaki; Iwamura, Takamichi; Saishu, Sadanori*; Urakami, Masao*; Masuda, Naohiro*; Yamauchi, Yuki*; Otani, Junichi*; et al.
JAERI-Tech 2001-053, 19 Pages, 2001/08
JAERI-Tech-2001-053.pdf:2.48MB
no abstracts in English
Kakuta, Tsunemi; Yamagishi, Hideshi; Tabata, Hiroaki*; Urakami, Masao*
Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.254 - 257, 2000/11
no abstracts in English
Shimizu, Michio; Iwamatsu, Shigemi; Takada, Fumiki; Sozawa, Shizuo; Kawamata, Kazuo; Oshima, Kunio; Tsuchiya, Kunihiko; Yamaura, Takayuki; Matsui, Yoshinori; Iwai, Takashi; et al.
JAERI-Tech 2000-029, p.48 - 0, 2000/03
JAERI-Tech-2000-029.pdf:9.26MB
no abstracts in English
Yamagishi, Hideshi; Suzuki, Katsuo; Kakuta, Tsunemi; ; *; *
JAERI-Research 99-002, 18 Pages, 1999/01
JAERI-Research-99-002.pdf:1.16MB
no abstracts in English
Hayashi, Kimio; Sawa, Kazuhiro
Nihon Genshiryoku Gakkai Dai-14-Kai 'Kaku Nenryo-Kaki Semina' Tekisuto, p.1 - 21, 1999/00
no abstracts in English
Yamagishi, Hideshi; Suzuki, Katsuo; Kakuta, Tsunemi;
JAERI-Research 98-063, 21 Pages, 1998/11
JAERI-Research-98-063.pdf:1.17MB
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
Isozaki, Kazunori;
PNC TN9410 97-062, 169 Pages, 1997/05
Sodium leak accident of MONJU was caused high cycles fatigue damage of thermometer well by flow-induced vibration. It was due to the sy㎜etric vortex shedding which was occurred rear flow of thermometer well. So, Thermometer wells installed in primary and secondary heat transport systems of JOYO were evaluated of flow-induced vibration. Evaluation of flow-induced vibration of thermometer well was done checking of flow-induced vibration base on authorized design report for JOYO, evaluation of summary flow-induced vibration by natural frequency of thermometer well in sodium as cantilever models, and evaluation based on small velocity rule of ASME Code Section III Appendix N-1300. By this result, thermometer wells (12B piping of secondary cooling system) were not sattisfied requirement to avoid flow-induced vibration by small velocity rule. Therfore, Detailed vibration characteristic analysis, water flow-induced vibration test, dumping test and evaluation of structural integrity were carried out. These results, vibration amplitude of well on the tip was 0.13mm (vibration non-dimensional amplitude of 0.015) and peak stress of 2.9kg/mm
is occurred. Thermometer wells (12B piping of secondary cooling system) which occurred peak stress by flow vibration was confirmed enough to satisfy 5.3kg/mm2 of design fatigue limit.
Katagiri, Masaki
Hoshasen, 23(3), p.3 - 15, 1997/00
no abstracts in English
Nishi, Hiroshi; ; Eto, Motokuni
Transactions of 14th Int. Conf. on Stuructural Mechanics in Reactor Technol. (SMiRT-14), 4, p.455 - 462, 1997/00
no abstracts in English
Aoyama, Takafumi;
PNC TN9420 96-058, 27 Pages, 1996/10
This report introduces the nuclear instrumentation system and the major radiation measurement techniques used in the Experimental Fast Reactor "JOYO". In the introduction of the nuclear instrumentation system, system function and role as reactor plant equipment, specifications and characteristics of neutron detectors, and layout of the system are described. Reactor dosimetry was used to evaluate neutron dose and their spectra for various irradiation tests and surveilance tests performed in JOYO. The multiple-foil activation method which is currently used and the Helium Accumulation fluence Monitor (HAFM) under development are described. The fuel failure detection (FFD) and the failed fuel detection and location (FFDL) systems in which radiation measurement plays a key role are introduced. It was shown some of the major experimental results obtained from a series of fuel failure simulation tests performed in JOYO. Finally, as a new radiation measurement technique, the Plastic Scintillation Fiber (PSF) is described which is a position sensitive radiation detector that can detect the radiation dose rate at the relevant position in the fiber. The PSF is used to upgrade the gamma-ray distribution measurement to accurately evaluate the Corrosion Products (CPs) behavior in the JOYO primary coolant system.
; ; 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.
Saito, Junichi; Hoshiya, Taiji; ;
JAERI-Tech 96-015, 58 Pages, 1996/03
no abstracts in English
H.V.Brixy*; Kakuta, Tsunemi
JAERI-Review 96-003, 77 Pages, 1996/03
JAERI-Review-96-003.pdf:3.21MB
no abstracts in English
