論文
オーステナイト系ステンレス鋼溶接継手の金属組織と 残留応力に及ぼす実機での高温長時間使用および補修溶接の影響
著者:
小原 智史,Satoshi OBARA,高屋 茂,Shigeru TAKAYA,若井 隆純,Takashi WAKAI,浅山 泰,Tai ASAYAMA,鈴木 裕士,Hiroshi SUZUKI,齊藤 徹,Toru SAITOH,Laurent MARTIN
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For the commercialization of fast breeder reactors (FBR), it is essential to enhance the economic competitiveness by reduction of total cost by elongation of plant service period. In this point of view, it is important to establish the assessment method of integrity of aged weld joint and repair welding for the components of future long life FBR. In the present study, evolution of microstructure is evaluated for the 304SS-304SS weld joint which was used for 88,000h at 526-545°C in the French proto-typ...
英字タイトル:
Influence of FBR plant service and repair welding on microstructure and residual stress of austenitic stainless steel weld joint
第14回
ショットピーニング時の残留応力緩和挙動に関する検討
著者:
木谷 悠二,Yuji KITANI,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,山田 祐介,Yusuke YAMADA,西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA
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In nuclear power plants, surface treatment including the shot peening is carried out after welding for the prevention of stress corrosion cracking. In this research, the authors developed evaluation systems of the persistence of compressive residual stresses due to shot peening based on the Idealized Explicit FEM which can conduct large-scale non-linear structure analyses in realistic computing time. The developed evaluation system was applied to the analysis of the compressive residual stress due to sho...
英字タイトル:
Study of behaver to relieve residual stress at the time of the shot peening
第5回
中性子残留応力測定法を用いた実機経年化溶接継手および補修溶接継手の健全性評価に関する基礎的検討
著者:
小原 智史,Satoshi OBARA,高屋 茂,Shigeru TAKAYA,若井 隆純,Takashi WAKAI,浅山 泰,Tai ASAYAMA,鈴木 裕士,Hiroshi SUZUKI,齊藤 徹,Toru SAITOH
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For the commercialization of fast breeder reactors (FBR), it is essential to enhance the economic competitiveness by reduction of total cost by elongation of plant service period. For this reason, it is needed to establish the aged weld joint integrity assessment method for future FBR compon ents. Additionally, since it is expected to employ the repair weld for aged structural components, it is essential to investigate the effect of repair weld. To investigate the influence of high temperature-long service...
英字タイトル:
Basic investigation of aging weld joint and repair weld joint integrity assessmentusing neutron residual stress measurement method
第14回
応力改善工法で付与した圧縮残留応力の持続性評価-ショットピーニングを施した溶接継手の熱サイクル及び応力負荷による残留応力変化(第2報)
著者:
西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA, ハルヨ ステファヌス,Stefanus HARJO,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,木谷 悠二,Yuji KITANI,山田 祐介,Yusuke YAMADA
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To validate the FEM simulation technique presented in the previous report, we made pipe butt welded joints between base metals of the same material SUS316L and between base metals of the dissimilar materials SUS316L and STPT370. Shot peening (SP) on the outer surface or the inner surface of these welded joints induces high compressive residual stresses on the surface. After heat treatment with the peak temperature of 623 K was applied to the welded joints, they retained high compressive residual stresses ...
英字タイトル:
Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method (the second report) ?Residual stress change of welded joint with shot peening by thermal cycle and stress loading.
第14回
応力改善工法で付与した圧縮残留応力の持続性評価-理想 化陽解法 FEM を用いたショットピーニング解析手法の開発 (第 1 報)
著者:
山田 祐介,Yusuke YAMADA,柴原 正和,Masakazu SHIBAHARA,生島 一樹,Kazuki IKUSHIMA,木谷 悠二,Yuji KITANI,西川 聡,Satoru NISHIKAWA,古川 敬,Takashi FURUKAWA,秋田 貢一,Koichi AKITA,鈴木 裕士,Hiroshi SUZUKI,諸岡 聡,Satoshi MOROOKA
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When the steel structure is built such as nuclear power plant, residual stress occurs in or near the welding joint and it may cause the stress collision cracking(SCC). Therefore, as prediction of SCC, surface treatment such as the shot peening(following SP) is carried out in the weld, but the case analyzed about residual stress reforming by the SP does not exist. So, we developed the analysis method that can predict compressive residual stress relaxation behavior during shot peening by modelling dynami...
英字タイトル:
Evaluation of the sustainability of compressive residual stress by introduced a stress improvement method (the first report) -Development of analysis method of the shot peening using idealized explicit FEM
第14回
断層変位に対するリスク評価と工学的な対応策 (4)機器・配管系の解析評価事例
著者:
佐藤 邦彦,Kunihiko SATO,鈴木 優,Yutaka SUZUKI,新間 聡,Satoshi SHINMA,原口 龍将,Ryusuke HARAGUCHI,神谷 昌伸,Masanobu KAMIYA,小川 勤,Tsutomu OGAWA,上屋 浩一,Koichi KAMIYA
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The structural integrity of equipment and piping systems to a fault displacement depends on the damage state of a reactor building. When there is no damage in a reactor building, the supporting function of equipment and piping systems is maintained. In this case, FEM analysis can estimate the allowable state of the entire system of the important safety equipment. In this part, an example of the analysis evaluation for the equipment and piping systems, which are important for safety, in the case of loading a...
英字タイトル:
Risk Evaluation Method for Faults Displacement by Engineering Approach (4)The Analysis Evaluation of Equipment and Piping System
第5回
核融合実験炉ITER用ダイバータ受熱機器における非破壊検査技術の開発
著者:
江里 幸一郎,Koichiro EZATO,鈴木 哲,Satoshi SUZUKI,大楽 正幸,Masayuki DAIRAKU,横山 堅二,Kenji YOKOYAMA,秋場 真人,Masato AKIBA
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Non-destructive examination (NDE) methods for joint interfaces between different materials in high heat flux components of ITER divertor should be urgently developed to assure qualit y and reliability of joining techniques. This paper reports the present R&Ds status of NDE for ITER divertor and its outlook. The detection ability of joint defect by using ultrasonic wave and thermography NDE are examined in the joint interface between armor tiles and a cooling tubes of divertor mock-ups. The results of both ...
英字タイトル:
Development of Non-destructive technique for ITER divertor high heat flux component
第5回
赤外熱画像を用いた核融合実験炉ダイバータ用非破壊検査装置の開発
著者:
横山 堅二,Kenji YOKOYAMA,鈴木 哲,Satoshi SUZUKI,江里 幸一郎,Kouichiro EZATO,関 洋治,Yohji SEKI,榎枝 幹夫,Mikio ENOEDA,秋場 真人,Masato AKIBA
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An infrared thermography NDE facility which is utilized in the acceptance test of ITER d ivertor components has been developed in JAEA. This NDE facility can inspect the integri ty of the bonding interface of the divertor components based on its surface temperature response by means of switching of hot (95 deg C)/cold (5 deg C) water. The advantages of this facility are 1) to have active coolant purging system which enables rapid temperatu re change and 2) to inspect the surface and the both side walls of...
英字タイトル:
Development of a non destructive evaluation system using infrared images for divertor on nuclearfusion experiment reactor