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
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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1回
ステンレス鋼配管超音波探傷技術
著者:
増本 光一郎,Koichiro MASUMOTO,斉藤 徹哉,Tetsuya SAITO,松浦 貴之,Takayuki MATSUURA,黒川 正秋,Masaaki KUROKAWA,川浪 精一,Seiichi KAWANAMI
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Abstract In the nuclear power plants, the reservation of safety and before-it-happens prevention of a trouble are important themes. Moreover, in connection with the life extension of a plant, life-expectancy diagnosis has also been an important subject. Although it is technology required in order that a non-destructive test may secure the safety of a power generation plant, Ultrasonic Testing (UT) is applied. However, generally the welding of stainl ess steel piping used widely in the PWR type nuclear powe...
英字タイトル:
Ultrasonic Testing Technique for Stainless Steel Pipe
第6回
セーフエンド溶接部に対するUTサイジング手法の高度化
著者:
西田 純一朗,Jun-ichiro NISHIDA,川浪 精一,Seiichi KAWANAMI,黒川 政秋,Masaaki KUROKAWA,井手尾 光司,Mitsushi IDEO,松浦 貴之,Takayuki MATSUURA,平野 伸郎,Shinro HIRANO,瀬良 健彦,Takehiko SERA
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In Japan, the preventive maintenance task of the 600 series nickel basis alloy weld of the reactor vessel (RV) and the steam generator (S/G) safe end weld are pushed forward sequentially, and a defect sizing using the ultrasonic testing (UT) from the inside of the safe end is carried out when the defect was dete cted by surface inspection prior to the work. Some defects are recognized on the S/G safe end and the R/V safe end in Japan, and these defects have occurred in the axial direction of the safe end w...
英字タイトル:
Development of Advanced Defect Sizing Technique Using Ultrasonic Testing for Nozzle Welding
第3回
フェーズドアレイ UT の RV セーフエンドへの適用
著者:
西田 純一朗,Jun-ichiro NISHIDA,浅田 義浩,Yoshihiro ASADA,増本 光一郎,Koichiro MASUMOTO,村上 平八朗,Heihachiro MURAKAMI,川波 精一,Seiichi KAWANAMI
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In the nuclear power plant, ultrasonic testing is performed as an in-service inspection of the reactor vessel (RV-ISI) according to JSME code. MHI is using the advanced UT machine (A-UT machine) system to RV-ISI under the high radiatio n condition. RV-ISI is one of the critical path in ISI schedule, so it is strongly required to reduce the inspection t ime of RV-ISI. In this report, the counter measure to reduce RV-ISI period by using the phased array UT is described....
英字タイトル:
Application of Phased Array UT to RV Safe End Welds Inspection
第7回
フェーズドアレイUTによるセーフエンド部欠陥サイジング手法の高度化
著者:
西田 純一朗,Jun-ichiro NISHIDA,川浪 精一,Seiichi KAWANAMI,井手尾 光司,Mitsushi IDEO,松浦 貴之,Takayuki MATSUURA,千種 直樹,Naoki CHIGUSA,平野 伸郎,Shinro HIRANO,瀬良 健彦,Takehiko SERA
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Recently, preventive maintenance tasks for welding of safe-end nozzles of reactor vessels and steam generators of PWRs in Japan had been carried out sequentially. Before the maintenance tasks, inspection services were carried out and several crack indications were found by eddy current testing (ECT). These indications were found in the welding which made b y 600 series nickel base alloy and evaluated as stress corrosion cracks which were oriented to the axial direction of the nozzle. Then investigations to...
英字タイトル:
Development of the advanced phased array UT technique for accurate sizing of cracks in the nozzlewelding
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論文
原子炉容器上蓋管台ECT検査用の新しい薄型プローブの検証
著者:
難波 一成,Kazushige NAMBA,Non-Member 中井 正義 Masayoshi NAKAI Non-Member 神納 健太郎 Kentaro JINNO Non-Member 山口 岳彦 Takehiko YAMAGUCHI Non-Member 熊谷 肇 Hajime KUMATANI Non-Member 井原 亮一 Ryoichi IHARA Member 川浪 精一 Seiichi KAWANAMI Non-Member
発刊日:
公開日:
The probe to be applied for the inner surface of the CRDM tubing having a narrow portion of the reactor vessel, however existing probe is not applicable to the minimum gap 1.5 mm of the CRDM tubing. It is necessary to study further thinning of the probe while maintaining sufficient detectability and flaw direction discrimination. Therefore, a new coil system using pancake coils was developed. As a result of a verification test, it was confirmed that an EDM flaw of 0.2 mm in length, 0.2 mm in width and 0.2 m...
英字タイトル:
 Verification of new thin ECT probe for reactor vessel head nozzle