111件が見つかりました。

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第11回
炭素繊維シートの主排気筒ダクトの補修への適用
著者:
綿引 健二,Kenji WATAHIKI,川澄 裕之,Hiroyuki KAWASUM,八戸木 日出夫,Hideo YATOGI,伊波 慎一,Shinichi INAMI
発刊日:
公開日:
キーワードタグ:
Off-gas of Tokai Reprocessing Plant, including gaseous radio-active elements, has been emitted from main stack after through exhaust duct. There were corrosion and crack at the part of the iron exhaust duct near the main stack. Repairin g method was planned to be used iron plate covering the corroded and cracked area, which would be attached and welded. To take into considering of reducing the weight of the attachment, much lighter materials namely carbon fiber reinfo rce polymer, CFRP, was applied except ...
英字タイトル:
Adaptation of the main duct maintenance technology used by Carbon Fiber Reinforce Polymer (CFRP)
第11回
照射劣化の中性子照射場依存性に関する数値解析
著者:
中筋 俊樹,Toshiki NAKASUJI,山本 泰功,Yasunori YAMAMOTO,森下 和功,Kazunori MORISHITA
発刊日:
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Since structural materials used in a fission reactor are subjected to irradiation by high energy neutrons, materials degradation due to irradiation should be taken into account when reactor design and maintenance are made. One of significant issues to be solved for a realization of long term operations beyond 40 years is to clarify the validity of a predictio n of material’s degradation due to long term irradiation that is not experienced yet. Material’s behavior due to 60 years irradiation in a reactor sh...
英字タイトル:
Numerical evaluation of radiation damage in metals under various neutron irradiation conditions
第11回
熱力学モデルによる福島第一原子力発電所1 号機 非常用凝縮器（IC）挙動の推定 （それでもIC は動いていた）
著者:
円山 重直,Shigenao MARUYAMA
発刊日:
公開日:
キーワードタグ:
In order to investigate the process of Accident of Fukushima Nuclear Plants, an accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 1 is analyzed from the data open to the public. Phase equilibrium process model and adiabatic expansion model were introduced. Original data reported in the first stage of the accident were examind to clalify the behaviour of the isolation condensers (ICs) which are generally believed unfunctional after the arrival of Tsunami and station blackout. The original...
英字タイトル:
Behaviour of isolation condensers (ICs) in accident of Fukushima Daiichi Nuclear Power Plant, Unit 1, based on thermodynamic model (And yet, the IC was working after Tsunami arrival)
第11回
熱力学モデルによる福島第一原子力発電所3 号機高圧注水系（HPCI）挙動の推定
著者:
円山 重直,Shigenao MARUYAMA
発刊日:
公開日:
キーワードタグ:
Inorder to clarify the process of Accident of Fukushima Nuclear Plants, an accident scenario of Fukushima Daiichi Nuclear Power Plant, Unit 3 is analyzed from the data open to the public. Phase equilibrium process model was introduced in which the vapor and water are at saturation point in the vessels. The present accident scenario assumes that the high pressure coolant injection system (HPCI) did not worked properly, but the steam in the reactor pressure vessel (RPV) leaked through the turbine of HPCI...
英字タイトル:
Behaviour of high pressure coolant injection system (HPCI) in accident of Fukushima Daiichi Nuclear Power Plant, Unit 3, based on thermodynamic model
第11回
理想化陽解法FEM を用いた実機多パス溶接継手の残留応力解析
著者:
西川 聡,Satoru NISHIKAWA,生島 一樹,Kazuki IKUSHIMA,柴原 正和,Masakazu SHIBAHARA
発刊日:
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In welds of steel structure of nuclear power plants, stress corrosion cracking and fatigue cracking occur, and the residual stress due to welding becomes one of the main factors causing them. Therefore, it is necessary to understand the residual stress distribution of a welded region, and residual stress analysis performed by the finite element method (FEM) has been become an effective tool. Previously, in order to shorten computation time, the analyses are carried out in a two-dimensional model and th...
英字タイトル:
Residual stress analysis of multi-pass welded joint in nuclear power plant using idealized explicit FEM.
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
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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11回
疲労健全性評価グランドデザインの構築(その 2) -国内実機疲労損傷事例分析-
著者:
中村 隆夫,Takao NAKAMURA,藤川 亮祐,Ryousuke FUJIKAWA,松下 幹弥,Mikiya MATSUSHITA,釜谷 昌幸,Masayuki KAMATA
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Abstract: After Fukushima-Daiichi NPP accident, improvement of nuclear safety is highly requested in order to prevent re-occurrence of severe accident. New sc me of fatigue evaluation to confirm system safety in NPPs is enhanced to be established based on Defense-in-Depth concept. In step 1, grand design of fatigue evaluation is reviewed on the viewpoint of fatigue management in long-term safe operation of NPPs, which is required after Fukushima-Daiichi NPP accident. Thi study focuses on the direction to r...
英字タイトル:
Reconstruction of Grand Design for Fatigue Evaluation (Step-2) -Fatigue failure analysis of Japanese NPPs-
第11回
疲労試験片表面観察に基づく 微小き裂の発生・成長に与える環境効果の影響評価
著者:
藤川 亮祐,Ryosuke FUJIKAWA,阿部 茂樹,Shigeki ABE,中村 隆夫,Takao NAKAMURA,釜谷 昌幸,Masayuki KAMAYA
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Fatigue life of nuclear facilities tends to be decreased by the influence of reactor coolant, which is called environmental effect. The effect accelerates crack growth rate but the influence for cra ck initiation is not clarified. This study intends to discuss the environmental effect in crack initiation. The crack length and the number of cracks are measured from the investigation of fatigue t est specimens in reactor coolant and air. The behavior of crack initiation is revealed from the measurement of nu...
英字タイトル:
Evaluations of environmental effect on micro crack initiation and propagation by surface observations of fatigue specimens
第11回
磁気センサを用いたインコネル600・SUS304 の 鋭敏化の非破壊評価
著者:
菊池 弘昭,Hiroaki KIKUCHI,柳原 宏樹,Hiroki YANAGIWARA,高橋 秀樹,Hideki TAKAHASHI,村上 武,Takeshi MURAKAMI
発刊日:
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Inconel 600 alloy, Ni base alloy, and SUS304 steel, austenitic stainless steel, are used for steam generators tubing, pressure vessel, etc. due to its high strength and high corrosion resistance. Stress corrosion cracking is attributed to sensitization at grain boundary occurs and it causes failures in plants. Though these alloys are paramagnet, they transforms into ferromagnetic along grain boundaries when sensitization occurs. Therefore nondestructive evaluation using magnetic measurement for sensiti...
英字タイトル:
NDE for sensitization of Inconel 600 and SUS304 using magnetic field sensor
第11回
福島事故と保全工学
著者:
岡本 孝司,Koji OKAMOTO
発刊日:
公開日:
キーワードタグ:
The Fukushima-Daiichi NPP Accident was caused by the wrong people and organization attitude for the nuclear safety. The Comprehens ive RISK is the most important factor to keep the safety for nucar system. However, the activities were based on the compliance only. Nobody consider the risk itself. To improve the experiences on RISK, all of the people and organization should always consid er the risk. The maintenance engineering based on the comprehensive risk will support the improvement of nuclear plant ex...
英字タイトル:
Maintenance Engineering considering Fukushima-Daiichi Accident
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