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第7回
クリープに伴う9Crフェライト系耐熱鋼の組織自由エネルギー変化
著者:
杉山 雄一,Yuichi SUGIYAMA,齋藤 良裕,Yoshihiro SAITO,村田 純教,Yoshinori MURATA,長谷川 泰士,Yasushi HASEGAWA
発刊日:
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キーワードタグ:
Microstructural state of metallic materials can be expressed by the system free energy, and the estimation of the system free energy is useful for the damage analysis of the materials. In this study, change in the system free energy of 9Cr heat resistant ferritic steels is estimated with cre ep time on the basis of Thermo-Calc calculation as well as a series of experiments such as X ray diffraction analysis, chemical analysis using ext racted residues, etc., and the change with creep time is expressed quan...
英字タイトル:
Change in the system free energy of 9Cr heat resistant ferritic steels with creep time
第7回
ステンレスにおける水素同位体透過挙動の解明
著者:
押尾 純也,Junya OSUO,倉田 理江,Rie KURATA,小林 真,Makoto KOBAYASHI,鈴木 優斗,Masato SUZUKI,王 万景,Wanjing WANG,大矢 恭久,Yasuhisa OYA,奥野 健二,Kenji OKUNO
発刊日:
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キーワードタグ:
Stainless steel is used in various nuclear installations as a major structural material. Tritium is produced by several nuclear reactions in these facilities. It is considered that the hydrogen isotope included tritium permeated for stainless steel through the interaction such as dissolution, diffusion and recombination, and is released on the atmosphere. Therefore, it is important to clarify permeation behavior of tritium in stainless steel from the viewpoint for improvement of the social acceptability o...
英字タイトル:
Study on permeation behavior of hydrogen isotope in stainless steel
第7回
ステンレス鋼溶接金属を透過したＵＴ(検出)確認試験研究の成果
著者:
永田 義昭,Yoshiaki NAGATA,長谷川 勝広,Katsuhiro HASEGAWA,久米田 正邦,Masakuni KUMEDA,稲垣 哲彦,Tetsuhiko INAGAKI,中田 親秀,Chikahide NAKADA,太田 隆,Takashi OHTA,田口 豊,Yutaka TAGUCHI,米谷 豊,Yutaka KOMETANI,清水 康,Yasushi SHIMIZU,三橋 忠浩,Tadahiro MITSUHASHI,東海林 一,Hajime SHOHJI,山口 篤憲,Atsunori YAMAGUCHI,杉林 卓也,Takuya SUGIBAYASHI,小林 輝男,Teruo KOBAYASHI
発刊日:
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BWR owners and plant fabricators have been making efforts to decrease the ISI parts where UT is difficult to be cond ucted. For that purpose, UT verification test for both detection and sizing qualification through deposit of pipe wel d joint started in 2009 and will last until 2011. In 2009, UT verification test for stainless steel pipe weld joint has been performed. Test samples are stainless steel pipes with welds and sizes are 600A.350A.150A with EDM notches a nd/or SCCs. Angle beam methods and phased...
英字タイトル:
Result of UT verification test for Stainless Steel through weld deposit
第7回
セラミックス材料の非破壊評価
著者:
西村 良弘,Yoshihiro NISHIMURA,近藤 直樹,Naoki KONDO,北 英紀,Hideki KITA,鈴木 隆之,Takayuki SUZUKI
発刊日:
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1 緒言カラー セラミックス部材はその剛性と耐熱性において金 属材料くらべ有利である. しかし,その破壊過程は 脆性的であり金属材料のそれと比べ急峻である. 破壊が始まってからではその進行を止めたり遅らせ たりすることはできない. そのため製造直後の欠 陥検査が重要である。部材中の欠陥存在確率はその 体積に比例するので、フリーの大型部材を作成する」 ことは非常に困難である。また、大きな部材の欠陥 検査を行うことも容易ではない。この対策として欠 陥の少ないことが確認された小型部材を接着組み合 わせることで欠......
英字タイトル:
Study of non-destructive evaluation for ceramics materials
第7回
タングステン球充填式ジャケット放射線遮へい設備の開発・実用化
著者:
嶋津 幸英,Yukihide SHIMAZU,水磨 裕之,Hiroyuki MIZUMA,上田 剛士,Takeshi UEDA
発刊日:
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In the outage at nuclear power plant, we try to reduce radiation exposure by installing shields in the work at places of high radiation dose rate. Many of these shields consist of the sheets and plates of heavy metals, and it takes a longer time to install or remove them because heavy loads must be accompanie d. At our company, therefore, we have developed a tungsten balls charge method radiation shield system, can reduce the exposure and workload of its install ation/removal. We will further promote vari...
英字タイトル:
Tungsten balls charge method radiation shield system
第7回
ニッケル基600合金用被覆アーク溶接金属の高温高圧純水中の応力腐食割れ感受性に及ぼすCr濃度の影響
著者:
西川 聡,Satoru NISHIKAWA,大北 茂,Shigeru OKITA,山口 篤憲,Atsunori YAMAGUCHI,池内 建二,Kenji IKEUCHI
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キーワードタグ:
When their Cr contents were increased to the same level as those of the alloy 82(18-22mass%Cr), the weld metals of alloy 182(13-17mass%Cr) sustained only slight SCCs in the as-welded state, and no crack was detected after the post weld h eat treatment (SR+LTA) of stress relief annealing at 893 K followed by aging at 673 K. These results suggest that the higher Cr content of the alloy 82 is responsible for its higher resistance to SCC than that of the alloy 182. The carbi de, Nijo(Mn, Cr).Siz (G phase) was ...
英字タイトル:
Effect of Chromium Content on Stress Corrosion Cracking of Shielded Metal Arc Weld Metalfor 600 Type Alloy in High Temperature Pressurized Pure Water
第7回
ニッケル基600合金用被覆アーク溶接金属の高温高圧純水中の応力腐食割れ感受性に及ぼすC、Nb濃度の影響
著者:
西川 聡,Satoru NISHIKAWA,山口 篤憲,Atsunori YAMAGUCHI,曽我部 恵典,Keisuke SOGABE,三上 欣希,Yoshiki MIKAMI,望月 正人,Masahito MOCHIZUKI
発刊日:
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キーワードタグ:
The SCC susceptibility of the weld metal was evaluated from the maximum depth and number of cracks occurring during the CBB (Creviced Bent Beam) test in high temperature pressurized water using plate specimens cut from shielded metal arc weld metals. When the specimen received a heat treatment consisting of stress relief annealing (SR) for 72 ks at 893 K and subsequent ageing (LTA) for 720 ks at 673 K, however, the significant influences of the increases in C and Nb contents on the SCC susceptibility were...
英字タイトル:
Effects of C and Nb Contents on Stress Corrosion Cracking of Shielded Metal Arc Weld Metalfor 600 Type Alloy in High Temperature Pressurized Pure Water
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:
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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7回
ピーニングによる応力腐食割れ防止効果に関する研究
著者:
前口 貴治,Takahru MAEGUCHI,堤 一也,Kazuya TSUTSUMI,豊田 真彦,Masahiko TOYODA,太田 高裕,Takahiro OHTA,岡部 武利,Taketoshi OKABE,佐藤 知伸,Tomonobu SATO
発刊日:
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キーワードタグ:
In order to verify stability of residual stress improvement effect of peeing for mitigation of stress corrosion cracking in components of PWR plant, relaxation behavior of residual stress induced by w ater jet peening(WJP) and ultrasonic shot peening(USP) on surface of alloy 600 and its weld metal was investigated under various thermal aging and stress condition considered for actual plant operatio n. In the case of thermal aging at 320-380°C, surface residual stress relaxation was observed at the early st...
英字タイトル:
Study on mitigation of stress corrosion cracking by peening
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
発刊日:
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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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