第10回
Flaw Tolerance手法を用いた疲労評価手法の開発
著者:
朝田 誠治,Seiji ASADA,竹田 周平,Shuhei TAKEDA,平澤 泰治,Taiji HIRASAWA,齋藤 利之,Toshiyuki SAITO,齋藤 格,Itaru SAITO,堂崎 浩二,Koji DOZAKI
発刊日:
公開日:
キーワードタグ:
The JSME Committee on Power Generation Facility Codes is developing a fatigue evaluation method by flaw tolerance. The ASME B& PV Code Section XI has Non-mandatory Appendix L, which provides a flaw tolerance method for fatigue evaluation when a cumulati ve usage factor (CUF) of a component is greater than 1.0. In order to develop a flaw tolerance method for the JSME Codes, post ulated initial flaws, capability of nondestructive examination, compatibility to rules and flaw tolerance codes are discussed....
英字タイトル:
Development of Fatigue Evaluation Using Flaw Tolerance Method
論文
ステンレス鋼配管突合せ溶接継手の超音波探傷試験員に 対する教育・訓練の有効性に関する検討
著者:
平澤 泰治,Taiji HIRASAWA,小林 輝男,Teruo KOBAYASHI,牧原 善次,Zenji MAKIHARA,南 康雄,Yasuo MINAMI
発刊日:
公開日:
キーワードタグ:
The ultrasonic examination personnel are required to have high-level abilities such as defect detection, classification of detected echoes and so on, in the ISI of nuclear power plant in Japan. For that purpose, the examination personnel of the inspection companies are trained to learn and maintain these abilities. In general, the importance of education and training for the ultrasonic examiners is recognized. However, the effectiveness of education and training to enhance the abilities of the ultraso...
英字タイトル:
Study on effectiveness of education and training for ultrasonic examiner in austenitic stainless steel piping welds
第7回
ニッケル基合金溶接部の欠陥深さサイジングに対するフェーズドアレイUT法の適用性評価
著者:
平澤 泰治,Taiji HIRASAWA,福冨 広幸,Hiroyuki FUKUTOMI
発刊日:
公開日:
キーワードタグ:
Recently, it is reported that the primary water stress corrosion cracking (PWSCC) has been occurred at the nickel based alloy weld components such as steam generator safe end weld, reactor vessel safe end weld, and so on, in PWR. Defect detection and sizing is important in order to ensure the reliable operation and life extension of nuclear power plants. In the reactor vessel safe end weld, it was impossible to measure crack depth of PWSCC. The crack has occurred in the axial direction of the safe end wel...
英字タイトル:
Application of Phased Array UT Technique for Crack Depth Sizing on Nickel Based Alloy Weld
第9回
フェーズドアレイ UT によるニッケル基合金溶接部の欠陥深さ測定法の開発
著者:
平澤 泰治,Taiji HIRASAWA,岡田 久雄,Hisao OKADA,福冨 広幸,Hiroyuki FUKUTOMI
発刊日:
公開日:
キーワードタグ:
Recently, it is reported that the primary water stress corrosion cracking (PWSCC) has been occurred at the nickel based alloy weld components such as steam generator safe end weld, reactor vessel safe end weld, and so on, in PWR. Defect detection and sizing is important in order to ensure the reli able operation and life extension of nuclear power plants. In the reactor vessel safe end weld, it was impossible to measure crack depth of PWSCC. The crack was detected in the axial direction of the safe end wel...
英字タイトル:
Development of Phased Array UT procedure for Crack Depth Sizingon Nickel Based Alloy Weld
第8回
フェーズドアレイ UT によるニッケル基合金溶接部の欠陥深さ測定要領の検討
著者:
平澤 泰治,Taiji HIRASAWA,岡田 久雄,Hisao OKADA,福冨 広幸,Hiroyuki FUKUTOMI
発刊日:
公開日:
キーワードタグ:
Recently, it is reported that the primary water stress corrosion cracking (PWSCC) has been occurred at the nickel based alloy weld components such as stea m generator safe end weld, reactor vessel safe end weld, and so on, in PWR. Defect detection and sizing is important in order to ensure the reliable operat ion and life extension of nuclear power plants. In the reactor vessel safe end weld, it was impossible to measure crack depth of PWSCC. The crack was dete cted in the axial direction of the safe end w...
英字タイトル:
Investigation of Phased Array UT procedure for Crack Depth Sizing on Nickel Based Alloy Weld
第5回
フェーズドアレイUTによる炉内配管への適用
著者:
平澤 泰治,Taiji HIRASAWA,湯口 康弘,Yasuhiro YUGUCHI,村上 功治,Koji MURAKAMI,大坪 徹,Tooru OOTSUBO,成瀬 克彦,Katsuhiko NARUSE
発刊日:
公開日:
キーワードタグ:
The improvement of defect detection and sizing capabilities for nondestructive inspection technique has been required in order to ensure the reliable operation and life extension of nuclear power plant . Immersion phased array UT technique which is not affected the surface geometry of welds has been developed for inspection of BWR internals such as shroud, shroud support, and so on. Furthermore, thin -type array probe was developed and was examined in UT of core spray piping welds in the narrow region betw...
英字タイトル:
Application of Phased Array UT on BWR Reactor Internals Piping
第3回
原子炉内構造物への超音波探傷技術の適用
著者:
平澤 泰治,Taiji HIRASAWA,長井 敏,Satoshi NAGAI,川原田 義幸,Yoshiyuki KAWAHARADA,村上 功治,Koji MURAKAMI,湯口 康弘,Yasuhiro YUGUCHI
発刊日:
公開日:
キーワードタグ:
The improvement of defect detection and sizing capabilities for nondestructive inspection technique has been required in order to ensure the reliable operation an d life extension of nuclear power plant. Phased array UT technique has superior capabilities for beam steering and focusing to objective regions, and real time B- scan imaging without mechanical scanning. Water gap phased array UT is capable to apply to inspection of welds of BWR internals such as shroud, shroud support, an d so on. Outline of TO...
英字タイトル:
Application of Phased Array UT in BWR Internals
第2回
炉内点検技術と高経年化プラントへの適用
著者:
山本 智,Satoshi YAMAMOTO,平澤 泰治,Taiji HIRASAWA,大坪 徹,Tooru OOTSUBO,落合 誠,Makoto OCHIAI,坂口 正武,Masatake SAKAGUCHI,亀山 育子,Ikuko KAMEYAMA
発刊日:
公開日:
キーワードタグ:
The request of the inspection to reactor internals is increasing with application of the Japanese operation and maintenance code to aged nuclear power plants. Toshiba has developed many outstanding under water inspection t echnologies combined with ultrasonic testing (UT) techniques and remote operated vehicles (ROVs) technologies. Water gap phased array UT technique is capable to apply to all internals including complicated form part such a s reactor bottom head penetration weldment. Laser-ultrasonic te...
英字タイトル:
Inspection Technologies for Reactor Internals of Aged Nuclear Power Plants
第11回
異種金属溶接部の付与欠陥に対する超音波探傷性能の検討
著者:
平澤 泰治,Taiji HIRASAWA,東海林 一,Hajime SHOHJI,秀 耕一郎,Koichiro HIDE
発刊日:
公開日:
キーワードタグ:
In recent years, it has been reported that the primary water stress corrosion cracking (PWSCC) has occurred in dissimilar metal weld (DMW) components such as steam generator nozzle to safe end weld, reactor vessel nozzle to safe end weld, and so on, in PWR. The depth sizing of such cracks with high accuracy is important in order to ensure the reliable operation and life extension of nuclear power plants. Therefore, construction of the performance demonstration (PD) system for certifying DMW inspection ...
英字タイトル:
Investigation of Equivalency of Ultrasonic Response Relation between SCC and Non-SCC Crack in Dissimilar Metal Weld
第10回
異種金属溶接部の溶接線平行欠陥に対する UT 深さ測定法の検討
著者:
平澤 泰治,Taiji HIRASAWA,福冨 広幸,Hiroyuki FUKUTOMI,秀 耕一郎,Koichiro HIDE
発刊日:
公開日:
キーワードタグ:
In recent years, it has been reported that the primary water stress corrosion cracking (PWSCC) has occurred in dissimilar metal weld (DMW) components such as steam generator safe end weld, reactor vessel safe end weld, and so on, in PWR. The depth sizing of such cracks with high accuracy is important in order to ensure the reliable operation and life extension of nuclear power plants. Therefore, construction of the performance demonstration (PD) system for certifying DMW inspection method is being inve...
英字タイトル:
Investigation of Phased Array UT technique for Circumferential Crack Depth Sizing in Dissimilar Metal Weld