148件が見つかりました。

並び替え
第6回
著者:
神保 吉秀,Yoshihide JIMBO,黒柳 克巳,Katsumi KUROYANAGI,瀬戸脇 浩友,Hirotomo SETOWAKI,肥田 茂,Shigeru HIDA
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This report describes the effectiveness of the application of acoustic diagnosis using vibration data for nspecting rotating machines. We usually apply the vibration diagnosis for the inspection of rotating machines on CBM(Condition Based Maintenance). However, with the vibration diagnosis, sometimes we annot discover the cause of abnormal sounds fro m rotating machines. Therefore, we tried another iagnosis. We converted the vibration data to the acoustic data and then inspected the abnormal sounds. We se...
英字タイトル:
Application of Acoustic diagnosis for rotating machines
第6回
著者:
宇佐美 照夫,Teruo USAMI,小島 史男,Fumio KOJIMA
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This study reports the development of automatic condition monitoring techniques and system. The techniques and the system have been developed to test industrial motors by their sound signals. In this study, several kinds of defects in motor can be detected using monitoring techniques. The programs make possible to compute diagnostic algorithm and to practice judgments correctly. This new condition monitoring method will be tested in some plant s and will be also applied to preventive maintenance for not on...
英字タイトル:
Monitoring of Rotating Machine in Plants
第6回
著者:
一宮 正和,Masakazu ICHIMIYA,山下 卓哉,Takuya YAMASHITA
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Prototype fast breeder reactor “Monju“ attained the first critical on April 5th in 1994. The sodium leak accident in a secondary main co oling system was occurred during power rise examination on December 8th in 1995, and the “Monju“ has stopped after that. Various efforts such as reconstruction of the secondary cooling system and following verifications on integrity of components and facilities are contin ued towards the early restart up of the “Monju“ at present. The current status and efforts on mainten...
英字タイトル:
Current Status of Monju and Effort on Maintenance 柳澤 務 Tsutomu YANAGISAWA
第6回
著者:
井上 正明,Masaaki INOUE,遠藤 寛,Hiroshi ENDO,伊東 智道,Tomomichi ITO
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JNES reviewed the accident management for the prototype fast breeder reactor Monju prepared by JAEA according to the direction of NISA. The validity of the accident management for Monju was evaluated from several view points; necessary conditions for t he achievement, the suitability of the event sequences applied by the measures, and the effect on the safety function and eval uation. In this paper, the evaluation of the influence of each accident management measures on the safety function is reported....
英字タイトル:
Accident Management Review of the Fast Breeder Reactor Monju
第6回
著者:
仲井 悟,Satoru NAKAI,向 和夫,Kazuo MUKAI
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The sodium leak accident in a secondary main cooling system of prototype fast breeder reactor Monju was occurred on December gth in 1995, and the Monju has stopped for 14 years since that. The confirmation of Monju systems and components integrity toward early restart of Monju was planned and started in 2006. The plan consists of inspection of components including repair, renewal and improvement and systems tests. About 90% of the integrity confirmation was comp leted at the end of May 2009. The integrity ...
英字タイトル:
Confirmation of Monju systems and components integrity and Maintenance Program toward Monju restart
第6回
著者:
林 晴久,Haruhisa HAYASHI,内城 憲治,Kenji UCHIJOU
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We performed the fatigue test of the rotary machinery bearing, and we compared t hemeasurement value of the vibration galvanometer (acceleration, speed, displace ment) with the measurement value of the shock pulse method. We examined the actu al machine applicability of the diagnostic technology by the shock pulse method...
英字タイトル:
Applicability study of the diagnostic technology by the shock pulse method
第6回
著者:
NGUYEN Thanh Duong ,Fumio KOJIMA
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This paper proposes a method for sizing pipe wall thinning, using pulse-echo EMAT modes. First, the proposed method deploys a compact simulator model to eff iciently reduce the computational cost of EMAT forward analysis. Then, an approach of signal processing based on peak values at back-wall echo and POD method is applied to EMAT signal are introduced. Finally, inverse analysis based on reduced POD basics is applied for defect parameters identification. Promising e xperimental results with high accuracy ...
英字タイトル:
Sizing methodology of pipe wall thinning using inverse analysis with EMAT signal
第6回
著者:
出町 和之,Kazuyuki DEMACHI,水口 明,Akira MIZUGUCHI
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In this study, the prediction method for time-series data was developed and its validity was verified by the comparison of the measured time-series and the predicted one. The measured time-series data was obtained as the laser displacemen t meter's output observing the human's chest movement during breathing. The Singular Spectral Analysis method (SSA) was applied as the prediction analysis method. The comparison showed good agreement of the measured and the predicted ones....
英字タイトル:
Diagnosis of Dynamic Equipments by SSA Method
第6回
著者:
菅沼 直孝,Naotaka SUGANUMA,松崎 謙司,Kenji MATSUZAKI,島村 光明,Mitsuaki SHIMAMURA,向井 成彦,Naruhiko MUKAI,笠井 茂,Shigeru KASAI
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This study proposes an algorithm for automatic generating motion trajectories of robot manipulator. This algorithm consists of two procedures. First, motion trajectories of the tool head are generated by using the concept of repulsive vector fields and motion trajectories model which consists of a number of spr ings and mass. Then, a posture of robot manipulator is also automatically generated using the same concept. We are planning to apply this system as a remote handling device for nuclear power plants....
英字タイトル:
Algorithm for Automatic Generating Motion Trajectories of Robot Manipulator in Nuclear Power Plant
第6回
著者:
細川 高憲,Takanori HOSOKAWA,決得 恭弘,Yasuhiro KETTOKU,林田 実,Minoru HAYASHIDA
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Condition Monitoring Technology such as vibration diagnosis, thermography diag nosis and oil diagnosis has been applied to a thousand of equipments in Ohi nuc lear power plant for about 10 years.This paper describes a summary of vibratio n diagnostic program and progress of condition monitoring process in our plant....
英字タイトル:
Establishment of Condition Monitoring Process of Vibration Diagnosis in Ohi Nuclear Power Plant