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第9回
磁気弾性結合効果を利用した鉄鋼材料の塑性変形の非破壊評価
著者:
藤井 裕嗣,Hiroshi FUJII,木下 勝之,Katsuyuki KINOSHITA,安部 正高,Masataka ABE,松本 英治,Eiji MATSUMOTO
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キーワードタグ:
Ferromagnetic materials have the interaction between mechanical and magnetic fields which is called the magnetomechanical coupling. Typical examples of such couplings are the magnetostriction and dependen ce of the stress strain relation on the magnetic field. The magnetoacoustic effect focused in this paper is also one of the magnetomechanical couplings. It has been shown that from the effect there exists the correlation of the plastic strain and the ultrasonic velocity change due to the magnetization. Th...
英字タイトル:
Non-Destructive Evaluation of Plastic Deformation of Steelusing Magnetoelastic Coupling Effect
第9回
福島事故後の原発耐震設計に対する北大学部生の評価
著者:
杉山 憲一郎,Ken-ichiro SUGIYAMA
発刊日:
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The sense of anxiety for safety of nuclear power plants among people in Japan has not disappeared after Fukushima Dai-ichi accident because of a typical country with frequent earthquakes. The provision of information for seismic design in nuclear power plants pr epared for easier comprehension is always required in any kind of study meetings for the social acceptance of nuclear power plants . In the present paper, the effect of the provision of information made an attempt for students in Hokkaido Universit...
英字タイトル:
Evaluation of Seismic Design by Students Made after Fukushima Dai-ichi Accident
第9回
福島事故後の立地地域住民とリスクコミュニケーション
著者:
土屋 智子,Tomoko TSUCHIYA
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Abstract A non-profit organization named HSE risk C-cube, continues risk communication activities to inform local residents in Tokai-mura how JAEA, NPP and nuclear fuel processing facilities had damages, recovered them and what they are improving. Also, the NPO researched what actions the off-site center for nuclear accidents and village office took after 3.11 earthquake. Members of the NPO were surpris ed the differences between what they were informed by nuclear licensees before the Fukushima accident an...
英字タイトル:
Local Residents and Risk Communication Activities after Fukushima
第9回
福島第一原子力発電所1号機事故の熱流動現象の推定-非常用復水器が作動していた場合-
著者:
円山 直,Shigenao MARUYAMA
発刊日:
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An accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 1 is analyzed from the data open to the public. The author assumed that the isolation condensers were partially func tional at the initial stage of the accident. The estimation describes that the rupture time of the pressure containment vessel was at 4:00 12/3/2011 and the rupture area was approxima tely 8 cm in equivalent diameter. The estimation show that the rupture time of the reactor pressure vessel was at approximately 6:00 12/3/2011...
英字タイトル:
Heat and Fluid Flow in Accident of Fukushima Daiichi Nuclear Power PlantUnit 1 - When the Isolation Condenser Was Working -
第9回
福島第一原子力発電所3号機事故の熱流動現象の推定―高圧注水系(HPCI)が途中で止まった場合一
著者:
円山 直,Shigenao MARUYAMA
発刊日:
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An accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 3 is analyzed from the data open to the public. The author assumed that the high pressure coola nt injection system stopped before TEPCO stopped it manually, and the vapor in the reactor pressure vessel is condensed in the condensate storage tank. The estimat ion describes that the rupture time of the reactor pressure vessel was at 8:55 13/3/2011. The estimation shows that the rupture time of the pressure containment ves sel was at 9:05 13...
英字タイトル:
Heat and Fluid Flow in Accident of Fukushima Daiichi Nuclear Power Plant, Unit 3- When the high pressure coolant injection system stopped -
第9回
等価応力振幅を用いた配管熱疲労評価法による評価結果の比較
著者:
鈴木 隆史,Takafumi SUZUKI,笠原 直人,Naoto KASAHARA
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In recent years, reports have increased about failure cases caused by high cycle thermal fatigue both at light water reactors and fast breeder reactors. One of the reasons of the cases is a turbulent mixing at a Tee -junction, where hot and cold temperature fluids are mixed, in a coolant system. In order to prevent thermal fatigue failures at Tee-junctions, The Japan Society of Mechanical Engineers published the guideline which is an evaluation method of high cycle thermal fatigue damage at nuclear pipes. ...
英字タイトル:
Comparison of Evaluation Results of Piping Thermal Fatigue EvaluationMethod based on Equivalent Stress Amplitude
第9回
米国高速炉廃材を用いた照射下ミクロ組織の非破壊検査技術開発(1) 実験的検討
著者:
匂坂 充行,Mitsuyuki SAGISAKA,江藤 淳二,Junji ETOH,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
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Development of methods of detecting degradation of irradiated reactor structural materials is required for successful operation of nuclear power plants. Ultrasonic waves, currently used as a non-destructive technique to detect cracks, change as a result of interacting with microstructural components and can be employed to measure radiation-induced changes in microstructure. Bulk-averaged measurements of microstructural changes can be determined usi ng ultrasonic velocity, attenuation and back-wall echo, wh...
英字タイトル:
Development of non-destructive inspection technique for microstructuresunder irradiation using decommissioned materials(1) An experimental approach
第9回
米国高速炉廃材を用いた照射下ミクロ組織の非破壊検査技術開発(2)理論的検討
著者:
江藤 淳二,Junji ETOH,匂坂 充行,Mitsuyuki SAGISAKA,松永 嵩,Takashi MATSUNAGA,枝川 文哉,Humiya EDAGAWA,礒部 仁博,Yoshihiro ISOBE,沖田 泰良,Taira OKITA
発刊日:
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キーワードタグ:
Abstract It is desired to develop an ultrasonic inspection technique non-destructively measuring various forms of irradiation-induced degradation in structural components of nuclear reactors. In order to evaluate the depth distributions of ir radiation-induced microstructural changes, we have developed a numerical simulation model of ultrasonic wave changes caused by microstructural changes in austenitic stainless steel based on the developed theory of ultrasonic wave propagation for comparison with experi...
英字タイトル:
Development of non-destructive inspection technique for microstructures under irradiation using decommissioned materials(2) An theoretical approach
第9回
膜分離活性汚泥処理装置による 原子力プラント洗浄排水処理
著者:
塚本 雅昭,Masaaki TSUKAMOTO,小華 和治,Osamu KOHANAWA,衣笠 敦志,Atsushi KINUGASA,小川 尚樹,Naoki OGAWA,室垣 健太,Kenta MUROGAKI
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In nuclear power plant, the radioactive effluent generated by washing the clothes worn in controlled area and the hand and shower water used at the controlled area are treated in laundry drain treatment system. Although various systems which treat such liquid waste preexist, the traditional treatment system has disadvantages such as high running cost and a large amount of secondary waste generation. To solve these matters, we have considered applicat ion of an activated sludge system, membrane bio reactor,...
英字タイトル:
Nuclear Power Plant Laundry Drain Treatment using Membrane Bio Reactor
第9回
表面加工層を有する SCC 発生試験片の応力および塑性ひずみ分布評価
著者:
三浦 靖史,Yasufumi MIURA,宮原 勇一,Yuichi MIYAHARA,加古 謙司,Kenji KAKO,佐藤 勝,Masaru SATO,鈴木 賢治,Kenji SUZUKI
発刊日:
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In this study, creviced bent beam (CBB) test, x-ray stress measurement, and hardness testing on a specimen made of Type 316L stainless steel with controlled plastic strain distribution were carried out in order t o clarify behavior of crack initiation and effects of plastic strain and stress distribution on SCC initiation. The following results were obtained. (1) In this SCC test, it was found that only micro cracks whose depths were smaller than 50um were observed until 200 hours and cracks whose depths w...
英字タイトル:
Evaluation of stress and plastic strain distribution on SCC initiation test piecewith surface work hardened layer
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