第3回
BMI 管台 J溶接部における検査技術の開発
著者:
木村 是,Tadashi KIMURA,東 正剛,Masayoshi HIGASHI,川浪 精一,Seiichi KAWANAMI,七田 知紀,Tomonori SHICHIDA,浅田 義浩,Yoshihiro ASADA
発刊日:
公開日:
キーワードタグ:
Recently, operation life of nuclear power plants is being extended, therefore, the maintaining the reactor vessel integrity is one of the most important matters in Japan. In these years, some leakages from penetration of alloy 600 CRDM and BMI were reported. B MI penetration is becoming one of the most critical issues in PWR components.In this paper, we introduce four new inspection techn iques including Visual testing (VT), Eddy current Testing (ECT), Adaptive Focusing UT (AdF-UT) and SAFT-UT for the BMI ...
英字タイトル:
Development of Inspecting Techniques for BMI J-Welds of PWR Nuclear Power Plants
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
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 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]
第10回
アレイ型プローブを用いた SG 二次側管支持板監視手法の開発
著者:
小橋 優司,Yuji KOHASHI,七田 知紀,Tomonori SHICHIDA,川瀬 直人,Naoto KAWASE,松浦 貴之,Takayuki MATSUURA,川田 かよ子,Kayoko KAWATA
発刊日:
公開日:
キーワードタグ:
Array ECT probe called Intelligent ECT probe (I-Probe) has a capability to inspect tubes of Steam Generator (SG) more productively and more accurately than conventional probes. It has been applied as full length inspection in Japan since 2003 and there is much field experience to date. On the other hand, a phenomenon in SG secondary side is known that scale deposits on the clog holes of quatrefoil type tube support plate(TSP). Water level oscillation of secondary side caused by excessive blockage of sc...
英字タイトル:
Development of Monitoring Method for SG Secondary Side Tube Support Plate Using Array Probe
第3回
インテリジェント ECT の実機適用
著者:
浅田 義浩,Yoshihiro ASADA,川田 かよ子,Kayoko KAWATA,川瀬 直人,Naoto KAWASE,七田 知紀,Tomonori SHICHIDA,高次 正弥,Masaya TAKATSUGU
発刊日:
公開日:
キーワードタグ:
The Intelligent ECT probe has been developed to achieve high speed inspectio n and high flaw detectability compared with conventional ECT probe. Intellig ent ECT probe has 24ch multi array coils which consist of inclined drive coi ls and thin-film pick-up coils and has various diameter types for inspectio n of various steam generators. In Japan, Intelligent ECT has been applied to 100% full length inspection of actual plants with fully automatic data acqu isition system. The Intelligent ECT has been applie...
英字タイトル:
Field experience with intelligent ECT