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第7回
Experiments of Influencing Factors in the Magneto-mechanical Effect
著者:
LiQiang ZHONG,LuMing LI
発刊日:
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キーワードタグ:
Based on the magneto-mechanical effect, the surface magnetic field of ferromagnetic materials can be used o evaluate their stress status or defects. However, there are several factors which affect the magnetic field listribution. In the last 10 years, we have carefully studied the effect of stress, the environmental field, and he material of the specimens. The experimental results pointed out some relationships between the surface ield and the structural safety of ferromagnetic materials: -. The abnormal c...
英字タイトル:
Experiments of Influencing Factors in the Magneto-mechanical Effect
第7回
FDTD法を用いたガイド波検査シミュレータの構築とその非破壊検査への応用
著者:
小島 史男,Fumio KOJIMA,古澤 彰憲,Akinori FURUSAWA,長谷 一輝,Kazuki HASE
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This paper is concerned with development of guided wave simulator on piping diagnostic system. First, a mathematical model of inspe ction procedures is described by a set of dynamical linear elastic equations in three spatial dimensions. Secondly, the numerical s cheme of the inspection model is given by using FDTD method. Finally, some numerical experiments are shown in order to assure the ap plicability of the proposed scheme to piping test. ...
英字タイトル:
Development of Guided Wave Simulator using FDTD method and its Application toNondestructive Testing
第7回
Introduction of Some Researches on Electromagnetic NDT
著者:
Zhenmao CHEN,Toshiyuki TAKAGI
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Abstract: In this paper, some research activities performed by authors on the Electromagnetic Vondestructive Evaluation (ENDE) for materials and structures of nuclear and other industries are ntroduced. The major contents includes, theoretical and experimental studies on NDT of ultra-li ght material and structures, NDT methods for Thermal Barrier Coating (TBC) inspection, improvement en quantitative NDT method of Stress Corrosio n Crack (SCC), new inspection method for material legradation etc. Research me...
英字タイトル:
Introduction of Some Researches on Electromagnetic NDT
第7回
Keynote Lecture：International Strategies by Japan Society of Maintenology (JSM)
著者:
Kenzo MIYA
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公開日:
Basic Ideas(1) Continue the current activities (2) Keep pace with the new global trend (Nuclear Renaissance) a?￠ In the maintenance field a?￠ Disclose Japanese advanced maintenance technologies a?￠ Disperse the idea of maintenance systematization = Maintenology (3) Concrete actions Technical exchanges with China Internationalization of domestic meetings Categorization of Japanese maintenance technologies...
英字タイトル:
International Strategies by Japan Society of Maintenology (ISM)
第7回
Ni基合金溶接金属／低合金鋼境界部における組織的特徴とSCC進展挙動
著者:
阿部 博志,Hiroshi ABE,石澤 允,Makoto ISHIZAWA,渡辺 豊,Yutaka WATANABE
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SCC behavior near the fusion boundary of dissimilar weld joint with Ni-based weld metal and low alloy steel in high temperature water has been investigated with special attention on relation t o the characteristics of microstructure. From the results of CBB test (1.0 ppm-Na2SO4 and 8 ppm dissolved oxygen), it has been obvious that the LAS has no SCC susceptibility. On the other hand, Alloy182 in the weld samples have SCC susceptibility. Most of crack tips have located at the fusion boundary, and the penetr...
英字タイトル:
Characteristics of microstructure and SCC behavior near the fusion boundaryof Ni-base weld metal and low alloy steel
第7回
Numerical Simulation of Residual Stress Measurement with Acoustic Wave
著者:
Cuixiang Pei,Kaziuki Demachi
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Abstract: In this work, a FEM (finite element method) simulation program was used in the residual stress measurement with acoustic wave. The possibility of assessing the residua l stress, by using an EMAT (electromagnetic acoustic transducer) receiver for precise me asurement of the acoustoelstic effect on LCR wave, was investigated by simulation method....
英字タイトル:
Numerical Simulation of Residual Stress Measurementwith Acoustic Wave
第7回
PD資格試験開始から4年の実施状況
著者:
秀 耕一郎,Koichiro HIDE,笹原 利彦,Toshihiko SASAHARA,直本 保,Tamotsu JIKIMOTO,渡辺 恵司,Keiji WATANABE
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The PD Center at the Central Research Institute of Electric Power Industry (CRIEPI) commenced Performance Demonstrat ion examinations for flaw depth sizing of austenitic stainless steel pipes in March 2006. As of April, 2010, 26 exam ination courses have been completed and 31 out of 43 candidates passed the examination. The average error margin of the successful applicant of the PD examination to the seventh stage was 0.17 mm, and standard deviation was 2.0 mm....
英字タイトル:
Report on Performance Demonstration for depth sizing of SCC flow in austenitic stainless steel pipes
第7回
PWRプラントの高経年対策における環境疲労評価
著者:
中村 隆夫,Takao NAKAMURA,三山 彰一,Shoichi MIYAMAIURA
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Numbers of nuclear power plants have been operating for more than 30 years and some of them exceeding 40 years in Japan. In these ageing plants, fatigue evaluation has a significant measure in assuring the plant reliability. The environmental fatigue in light water reactors, which was first recognized i n the 1980's in Japan, has been drawing attention worldwide because it may cause remarkable effects on the life of important components.. This paper int roduces a few examples of environmental fatigue evalu...
英字タイトル:
Environmental Fatigue Evaluation in PLM Activities of PWR plant
第7回
PWR炉内構造物点検評価ガイドラインの概要[クラス1 容器 管台セーフエンド異材継手部]
著者:
七田 知紀,Tomonori SHICHIDA,西村 護達,Moritatsu NISHIMURA,廣 孝文,Takafumi HIRO,鈴木 晴登,Harutaka SUZUKI
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The damage caused by primary water stress corrosion crack (PWSCC) has been revealed in the Noz Safe-end with alloy 600 domestical ly and internationally in recent years. The guideline has been examined and studied to clarify the application of inspection tech niques and preventive maintenance method, the approach to the evaluation for acceptance level of continuous operation and inspect ion frequency. The summary of this guideline is introduced in this paper....
英字タイトル:
Summary of Guideline for Inspection and Evaluation of PWR Redactor Internal[Class 1 component Nozzle Safe-end dissimilar metal weld]
第7回
PWR炉内構造物点検評価ガイドラインの概要[原子炉容器炉内計装筒]
著者:
七田 知紀,Tomonori SHICHIDA,鈴木 晴登,Harutaka SUZUKI,吉田 有佑,Yusuke YOSHIDA
発刊日:
公開日:
キーワードタグ:
The damage caused by primary water stress corrosion crack (PWSCC) has been revealed in Reactor Vessel Head Penetration Nozzles with alloy 600 domestically a nd internationally in recent years. Bottom Mounted Instrumentation which has the same structure as Head Penetration Nozzle is also necessary to consider the occurrence of damage. The guideline has been examined and studied to clarify the application of inspection techniques and preventive maintenance method, the approach to the evaluation for acceptanc...
英字タイトル:
Summary of Guideline for Inspection and Evaluation of PWR Reactor Internal[Reactor Vessel Bottom-Mounted Instrumentation]
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