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第9回
オリフィス背後の物質輸送現象に及ぼす曲り旋回流の影響(ステレオ PIV を用いた速度場計測)
著者:
金谷 信明,Nobuaki KANATANI,山縣 貴幸,Takayuki YAMAGATA,藤澤 延行,Nobuyuki FUJISAWA
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Abstract The velocity field behind an orifice in a circular pipe is studied by PIV measurement u nder the influence of curved swirling flow to elucidate the asymmetric pipe-wall thinning pheno menon behind an orifice. The experiment is carried out in a closed water tunnel at Reynolds numb er Re = 19,000. The stereo PIV measurement of the cross-sectional velocity field in a pipe flow indicates that the flow reattachment occurs on one side of the pipe flow irrespective of the ori fice bias. This is due to th...
英字タイトル:
Influence of Curved Swirling Flow on Mass Transfer Phenomenon behind an Orifice(Velocity Field Measurement by Stereo PIV)
第9回
オーステナイトステンレス鋼における微小疲労き裂発生挙動と照)損傷の影響
著者:
中井 亮介,Ryosuke NAKAI,佐藤 佑毅,Yuki SATO,野上 修平,Shuhei NOGAMI,長谷川 晃,Akira HASEGAWA
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The effect of irradiation on slip band formation and growth and micro-crack initiation behavior under low cycle fatigue in SUS316L austenitic stainless steel was investigated using accelerator-based proton irradiation and a low cycle fatigue test at room tem perature in air. The micro-crack initiation was observed at slip band, grain boundary, twin boundary, and triple junction regardless of the total strain range and the proton irradiation. In unirradiated specimens, the micro-crack initiation life droppe...
英字タイトル:
Fatigue Micro-crack Initiation Behavior and Effect of Irradiation Damage on Itin Austenitic Stainless Steel
第9回
ショットピーニングを施したニッケル基合金溶接部 の熱履歴による圧縮残留応力と耐粒界腐食性の変化
著者:
西川 聡,Satoru NISHIKAWA,大井 浩一,Koichi OOI
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Shot peening process is countermeasures to prevent stress corrosion cracking in nuclear power plant components. It is necessary to confirm whe ther the compressive residual stress exerted by stress improvement processes can be sustained under operation environment. In order to evaluate stability of compressive residual stress, the nickel base alloy welded specimen was subjected to thermal cycles 10 times where the peak temper ature is 593 K. On the other hand, carrying out shot peening increases the interg...
英字タイトル:
Change of compressive residual stress and intergranular corrosion resistanceafter thermal history in nickel base alloy welds by shot peening
第9回
タービン制御油からのリン回収方法の検討
著者:
池堂 和仁,Kazuhito IKEDOU,春日 智子,Tomoko KASUGA
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When an EHC turbine oil used at a nuclear power plant was burned up in a furnace, a phosphorus-containing compoun d with a low-melting temperature formed to clog a ceramic filter for removing an effluent gas. In the present wor k the compound in the oil was converted into chemically stable phosphates via reaction with calcium hydrate at ro om temperature. The resulting calcium phosphates could be removed as a fly ash after heating at high temperature....
英字タイトル:
Examination of the phosphorus recovery method from turbine control oil.
第9回
チェルノブイリ事故の後処理対応及び我が国への教訓
著者:
藤井 有蔵,Yuzo FUJII
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After the accident of Chernobyl NPP #4 1986, various activities including the construction of the shelter, prevention of the release of radioactive dust and liquid from the shelter, monitoring the condition of the damaged core, and disposal of radioactive waste have been impl emented in the Chernobyl site for mitigating the nuclear and radioactive risks of damaged nuclear facilities, and the reducing radiation dose of working personnel. The construction of new shelter started for the decommissioning of the...
英字タイトル:
Post-processing Activities after Chernobyl Accident in Ukraine and LessonLearned to the Response on Fukushima Dai-Ichi Accident
第9回
ナトリウム冷却型 FBR 向け摩擦攪拌接合補修装置の開発
著者:
加藤 潤悟,Jungo KATOH,森本 将明,Masaaki MORIMOTO,篠原 種宏,Tanehiro SHINOHARA,堀 匠,Takumi HORI,渡部 裕二郎,Yujiro WATANABE,藤谷 泰之,Yasuyuki FUJIYA,道下 幸雄,Yukio MICHISHITA,中田 一博,Kazuhiro NAKATA
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An in-vessel repairing machine for Fast Breeder Reactor (FBR) needs to work under liquid sodium environment. W e have been worked the development of a repairing machine based on Friction Stir Welding (FSW) method. The expe riment of repairing artificial crack in liquid sodium was successful by prototype FSW-repairing machine. In th is report, we also introduce our studies on the particular problems of FSW-repairing such as burr and end hole....
英字タイトル:
Development of a repairing machine based on Friction Stir Welding (FSW) for the sodium coolant Fast Breeder Reactor
第9回
ハイビジョンカメラを用いた水中カメラの開発
著者:
辻 建二,Kenji TSUJI,渡邊 将人,Masato WATANABE,高島 政信,Masanobu TAKASHIMA,河村 真吾,Shingo KAWAMURA,田中 寛之,Hiroyuki TANAKA
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Abstract In order to reduce the time for core verification or visual inspection of BWR fuels, the underwater camera using a High- Definition camera has been developed. As a result of this development, the underwater camera has 2 lights and 370×400×328mm dimen sions and 20.5kg weight, Using the camera, 6 or so spent-fuel IDs are identified at lor 1.5m distance at a time, and 0.3mm $ pin-h ole is recognized at 1.5m distance and 20 times zoom-up. Noises caused by radiation less than 15Gy/h are not affected th...
英字タイトル:
Development of underwater camera using High-Definition camea
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
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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 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9回
プロアクティブ材料劣化潜在事象評価とシステム安全
著者:
庄子 哲雄,Tetsuo SHOJI,竹田 陽一,Yoichi TAKEDA,国谷 治郎,Jiro KUNIYA
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A Proactive Materials Degradation Management (PMDM) project has been carried out at the Fronti er Research Initiative (FRI), New Industry Creation Hatchery Center, Tohoku University for 5 ye ars, as a part of a Nuclear Industries Safety Agency (NISA) project that was originally formed in 2007 to define an Aging Management Program that addresses unexpected structural material fa ilures in Light Water Reactors (LWRs). Such a program required, therefore, the development of a life prediction capability for sp...
英字タイトル:
Proactive Evaluation of Potential/Latent Degradation Phenomena for Light Water Reactor Structural Materials and System Safety
第9回
ポアソン分布を用いた SCC 発生・進展の試算
著者:
渡士 克己,Katsumi WATASHI
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A Poisson distribution well represents SCC initiation and subsequent small scale growth in material tests. This report describ es the Poisson distribution application to LWR SCC database which was arranged from NUCIA. Frequencies were plotted against ope rated duration, then a Poisson's parameter was set to represent SCC aspect. In subsequent step, for one case of IASCC, a crack propagation was calculated. Fitting degrees of the distributions and a major parameter on failure probability were emphasized....
英字タイトル:
Calculation of SCC detection and growth using a Poisson distribution
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