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第7回
Remote Detection and High Precision Evaluation of Wall Thinning Volume in a Metal Pipe
著者:
Linsheng LIU, Yang JU
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We report a nondestructive method to measure the pipe wall-thinning (PWT) remotely using microwaves. A microwave vector network analyzer (VNA) and a self-designed transmitting and receiving (T&R) coaxial-line sensor are employed in the experi ment to generate microwave signals propagating in the metal pipe where the frequency was swept from 14.08 to 14.12 GHz. A brass pipe with inner diameter of 17.03 mm, 1.0 mm wall thickness, 2.0 m length, and connected respectively with 9 joints having the lengths of 17...
英字タイトル:
Remote Detection and High Precision Evaluation of WallThinning Volume in a Metal Pipe
第7回
Simulation for the Assessment of Wall Thinning using Eddy Current Method
著者:
程 衛英,Weiying CHENG,古村 一朗,Ichiro KOMURA
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A pipe with protective lagging and thermal insulation is modeled by a multi-layered structure. Sinusoidal or sed eddy current are induced by a circular coil held above the structure to measure the thickness of the pipe 11. Analytical solutions of both sinusoidal and pulsed eddy c urrent measurements are deduced. Parameters ecting the measurement are studied using the analytical solutions. Measurement conditions are di scussed ed on the analytical results. Keywords: wall thinning, muti-layered structure, ed...
英字タイトル:
Simulation for the Assessment of Wall Thinning using Eddy Current Method
第7回
US-APWR保安規定におけるリスク情報の活用
著者:
黒岩 克也,Katsuya KUROIWA,高橋 浩道,Hiromichi TAKAHASHI,佐治 悦郎,Etsuro SAJI
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A lot of Nuclear Power Plants in the US change Completion Time and Surveillance Frequency in the Technical Specifications with risk based insights. Above all, Risk-Managed Technical Specifications (RMTS) which can be approved to change flexibly the Completion Time with PSA re sults and Surveillance Frequency Control Program (SFCP) which can be approved to change flexibly the Surveillance Frequency with PSA resul ts are revolutionary Risk-informed Management methods. MHI have applied RMTS and SFCP methods ...
英字タイトル:
Application of risk based insights to US-APWR Technical Specifications
第7回
「もんじゅ」におけるナトリウム漏えい検出設備の保全活動
著者:
武藤 啓太郎,Keitaro MUTO
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Monju is sodium cooled Fast Breeder Reactor. Monju resumed operations on May 5th, 2010 after an intermission for about 14 years following a sodium leak accident. During the shut-down period, sodium s ystem was operated and there were some troubles of sodium leak detectors. To improve leak detectors performance and reliability, detectors modification and improved maintenance activities were applie d. For example, a contact type sodium leak detector (CLD) in the secondary sodium system was modified to increa...
英字タイトル:
Maintenance activities for sodium leak detection system in Monju
第7回
すべり軸受の早期ラビング検出技術について
著者:
迫 孝司,Takashi SAKO,徳茂 廣太郎,Koutaro TOKUMO
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1. はじめにすべり軸受は、タービンや高圧ポンプなどの大型 の回転機器や空気圧縮機などの高速回転機器に用 いられている重要な機械要素である。すべり軸受は 油膜により非接触状態で回転している為、転がり軸 受と比較すると異常の発生頻度は低いものの、施工 不良や熱変形、あるいは異常振動が原因でラビング (接触)が発生し、損傷に至ることがある。このラ ビング現象を軽微な段階で検出することができれ ば、すべり軸受の損傷を未然に防ぐことができる。 特に、石油化学や発電所などといった設備をすぐに は停止できないプラント......
英字タイトル:
Detection method for rubbing of sliding bearing in early stage
第7回
イメージベース波動伝搬シミュレーションと超音波探傷への応用
著者:
中畑 和之,Kazuyuki NAKAHATA,廣瀬 壮一,Sohichi HIROSE
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A straightforward simulation method is desired for the reliable nondestructive ultrasonic testing (UT). The target models for the UT become more complicated than ever, such as dissimilar welding parts in nuclear power plant or debonding parts of reinforced steels in concrete material. In this study, a time domain simulation tool for ultrasonic wave propagation in heterogeneous and anisotropic materials w ith a complex outer surface is developed by combining the elastodynamic finite integration technique (...
英字タイトル:
Image-based Simulation of Wave Propagation and its Application to Ultrasonic TestingMember
第7回
オリフィス下流における流れ加速腐食機構に関する実験的研究
著者:
小城 烈,Retsu KOJO,黒田 祐志,Yuji KURODA,近藤 昌也,Masaya KONDO,辻 義之,Yoshiyuki TSUJI
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Flow Accelerated Corrosion (FAC) is thought to be the origin of the pipe thinning in the pipe of second cooling system of power plants. FAC is a phenomenon that inclined to and promoted the c orrosion because of the increase of the complex turbulent flow behind the orifice. Now the analysis of the mechanism of FAC for maintenance of the nuclear reactor is performed. Although the r ough surface is confirmed over the pipe wall, influence of the shape on the corrosion is not understood at this stage. Therefor...
英字タイトル:
Experimental research on mass flow accelerated corrosion mechanism behind the orifice
第7回
オリフィス下流における流れ加速腐食機構に関する数値的研究
著者:
七條 慎太郎,Shintaro SHICHIJO,古谷 真伍,Shingo HURUYA,近藤 昌也,Masaya KONDO,辻 義之,Yoshiyuki TSUJI
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Abstract The accident to which the secondary system piping of the Mihama Power Station Unit-3 was damaged in August, 2004 happened. This is due to thinning of the pipe, and it is thought to be flow accelerated corrosion mechanism (FAC). The turbulence kinetic energy is considered as one of the flow factors in FAC. This is because the location where the amount of thinning is large and the parts where the turbulence kinetic energy is high are corresponding comparatively well. However, the causal relation bet...
英字タイトル:
Numerical research on flow accelerated corrosion mechanism behind the orifice-Numerical simulation close to the wall
第7回
オーステナイト系ステンレス鋼の高ひずみ速度による微視的残留応力
著者:
鈴木 賢治,Kenji SUZUKI,菖蒲 敬久,Takahisa SHOBU
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Austenitic stainless steel (SUS316L) was used as the specimen material. The specimens were deformed plastically with a wide range (6.7 x 10-5 ~ 670 s-1). The residual micro-stresses were measured using hard synchrotron X-ray. The residual micro-stress for each lattic e plane was arranged with Young's modulus, which was calculated by Kroner model. In the high strain rate, the change of the residual m icro-stress became small. The residual micro-stresses peened with laser and water-jet were examined as well ...
英字タイトル:
微視的残留力 Residual Microstress in Austenitic Stainless Steel due to High Strain Rate
第7回
カルマンフィルタを用いた流れ加速型腐食による減肉進展予測モデルの構築
著者:
小島 史男,Fumio KOJIMA,坪田 淳一,Junichi TSUBOTA,植田 正裕,Masahiro UEDA
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The purpose of this report is to establish a predictive methodology for estimating rate of wall thinning in a piping system used in ag eing nuclear power plants. First, mechanism of flow accelerated corrosion caused by steam of flowing water is given by KWU-KR model. Se condly, a method for setting geometrical parameter based on pipe wall thickness measurements is considered. Thirdly, estimation method ology for wall thinning rate is formulated within the framework of Kalman filtering. Finally, some simula...
英字タイトル:
Prediction of Wall Thinning by Flow Accelerated Corrosion using Kalman Filtering
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