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千葉 矩正, 大堀 雄太, 小笠原 永久, 白戸 和規, Xi Chen
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村田 直一, 玉川 欣治, 三浦 英生
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Fatigue fracture properties of electroplated copper thin films were measured under uni-axial stress loading. Two kinds of electroplated films were prepared for fatigue test. One was a commercial film mainly used for interconnections in printed wiring boards. The other film was grown on stainless steel substrate by using acid copper sulfate bath including no additive agent. The fatigue fractured surfaces were observed using SEM. It was found that the fracture mode of the films was quite different with each other. One was ductile and the other was brittle. In addition, the fatigue strength of the film grown on the stainless steel was about 1.5 times higher than that of .the commercial film. This was because of the difference of the micro texture between the two kinds of films.
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中村 恭輔, 脇 裕之, 山口 樹
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Protective coating is an indispensable technology of a gas turbine plant. High velocity oxygen-fuel (HVOF) spray is one of the coating processes. High temperature mechanical properties of thin protective coating have not been clarified because of the difficulty in measurement. The purpose of this study is evaluation of the high temperature mechanical properties of the protective coating. Lateral compression test for the circular tube coatings of HVOF-sprayed thin coating under various temperature conditions were carried out. Results are summarized as follows. (1) Young's modulus and bending strength decreased with an increase of temperature. Young's modulus suddenly dropped around 500℃. Bending strength suddenly dropped around 450℃. (2) The heat-treatment at the high temperature, such as 1100℃, is effective for the improvement of the mechanical property, such as Young's modulus and bending strength and fracture strain. (3) Atmospheric heat-treatment is effective for the improvement of Young's modulus and bending strength. Vacant heat-treatment is effective for the improvement of fracture strain.
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荒井 正行, 和田 英志, 岸本 喜久雄
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Thermal barrier coating (TBC) is applied to high-temperature components of land-based gas turbine(GT). In TBC fabricated by thermal plasma process, a spallation damage is ofen observed in the components, because of subjecting to cyclic stress due to start-steady-stop operation of GT. Thus, it is necessary to grasp stress generated in the coating during service, in order to predict precisely life of the TBC spallation. The coating stress is composed of residual stress formed by thermal plasma process and thermo-mechanical stress generated during the operation. The residual stress is especially known to take different value with dependence on themal spray conditions (powder velocity and substrate temperature). This paper presents influence of the spray condition on the residual stress of TBC. Then, the residual stress evaluation method, which has been already proposed, is extended based on particle deposition process modeling thermal spray process. As obtained results, it was found that the residual stress measured by strain gage method increased compressively with higher particle velocity. Influence of substrate temperature on the residual stress was very few. The residual stress evaluation was extended in consideration of the elastic modulus changing by particle velocity. The results estimated by the extended method agreed with one measured by the strain gage method.
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荒巻 徹, 青野 雄太, 野口 博司, 宮地 真也, 立川 俊洋, 陳 新衛, 茅本 隆司
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In a spray process, it is comfirmed that a temperature of residual stress'es generation has to be clarified for mechanism in generation of residual stress. But a mechanism of the temperature is largely-unexplored. And so in this report an estimation approach of residual stress is proposed through the viewpoint of energy consumption. By measurements of a surface temperature, a base temperature and a residual stress for 1 sample, a parameter for presuming a temperature of residual stress 'es generation is clear up. And residual stresses of other samples are presumed reasonably with the finite element analysis of thermal stress. Accordingly, it is clear up that the proposed estimation approach is reasonable. Based on the estimation approach, the control approach of residual stress is established. In addition, flowchart for residual stress'es control in product is presented. Accordingly, residual stress can be controlled reasonably.
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玉川 欣治, 村田 直, 三浦 英生
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In order to improve the sensitivity of stress measurement using an electroplated copper film, the mechanism of micro texture change of an electroplated copper thin film with a small square slit was discussed by observing the change of the film surface and by finite element analysis under an uni-axial loading. The electroplated film consisted of columnar structure with a diameter of about 0.5 μm and showed anisotropic mechanical properties. The recrystallization of the film started at the corner of the square slit and the change of the micro texture occurred only around the free surface of the film. This is because that the maximum strain due to the uni-axial loading appeared near the free surface of the film with a square slit.
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Pornthep Chivavibul, 渡辺 誠, 黒田 聖治
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Twelve commercially available WC-Co powders with different average carbide sizes (0.2, 2, and 6 μm) and cobalt contents (8, 12, 17 and 25 wt.%) were sprayed on carbon steel substrates using High Velocity Oxy-Fuel (HVOF) spraying. Hardness, fracture toughness and abrasive wear properties of the coatings were investigated. The hardness decreased with increasing cobalt content, while fracture toughness slightly increased. The effect of carbide size on the hardness showed no specific trend. The wear properties was studied using Suga-type wear tester and the results showed that coatings with finer carbide had a high wear rate than the coarser ones. These behaviors were discussed with the help of microstructure observations of the coatings by scanning electron microscopy, X-ray diffraction and chemical analysis.
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松本 峰明, 加藤 丈晴, 山口 哲央, 北岡 諭, 松原 秀彰
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笹川 和彦, 平野 悟
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Thermoelectric effect is an interaction of a thermal phenomenon and an electric phenomenon. The thermoelectric effects are enhanced if electric current with high-density flows in metal. On the other hand, high-density current induces electromigration, which means the transportation of metallic atoms by electron wind. In the metal under high-density current, the thermoelectric effects and electromigration take place at the same time, and it, therefore, is expected that electromigration has a concern with the thermoelectric effects. In this study, the effect of electromigration on the thermoelectric effects is discussed taking notice of the absolute thermopower which indicates the magnitude of the thermoelectric effects. Using Au/Ni thermocouple, the Seebeck electromotive force (EMF) is measured before and after the introduction of electromigration to metal. The value of thermopower is obtained from check the each Seebeck EMF. And the effect of electromigration on the thermopower of Au/Ni is discussed.
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小川 和洋, 市川 裕士
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福本 昌宏, 田部 心有, 山田 基宏, 伊澤 守康
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Self designed cold spray equipment was installed in the laboratory and deposition behavior of sprayed individual metallic particles on the substrate surface was fundamentally investigated. As a preliminary experiment, pure Cu particles were sprayed on mirror polished stainless steel substrate surface. Particles diameter, process gas, gas pressure, gas temperature and substrate temperature were systematically changed as the process parameters, and effect of these parameters on the flattening or deposition behavior of an individual particle was investigated. From the results obtained, it was found that the deposition temperature is a possible domination on the deposition behavior in cold spray process.
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片野田 洋
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In the numerical simulation of temperature of particles traveling in the jet flow of the cold spray, the particle temperature is usually assumed to be uniform. This assumption is valid for spray materials with larger thermal conductivity such as pure metals or alloys. For spray materials with smaller thermal conductivity, however, this assumption may not be valid. This paper numerically clarifies the spray conditions for which the assumption of the temperature uniformity of the particle is no longer valid in the cold spray.
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榊 和彦, 片野田 洋, 清水 保雄
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市川 裕士, 伊藤 潔洋, 小川 和洋, 庄子 哲雄
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The principle of cold spray is that the solid particle impacts and deposits on the substrate without melting and phase transformation. However, the cold spray deposition mechanism has not been clear yet. It is considered that the substrate surface condition has influence on the deposition behavior of cold spraying, and also surface condition may be changed by a large number of particle impinging. Several surface parameters such as surface roughness, hardness, temperature and micro structure are changed within particle impacts. In this study, in order to determine the most affective factor of cold spray deposition, the several times traversed and sprayed specimens were prepared. The surface activation was controlled by the interval time between traverses. The number of deposited particles on the substrate at the several interval times was investigated. From the results, it was confirmed that the surface activation is more important factor for cold spray deposition.
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深沼 博隆, 黄 尽忠
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In this study, Nickel, Aluminum and Copper coatings were deposited by Cold Spray process on three kinds of substrates, Al, Cu and Stainless Steel. The tensile strength of the coatings was tested and the hardness of the substrates was also measured. The influences of substrate hardness on the tensile strength were discussed. The influences of working gas temperature on the tensile strength were also discussed.
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北村 順也, 佐藤 和人, 青木 功, 榊 和彦, 高畑 宗晃, 清水 保雄
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鬼澤 光一郎, 川喜多 仁, 黒田 聖治, 篠原 正, 鈴木 雅人, 袖岡 賢, 坂本 幸弘
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温度を最適に制御した超音速粒子の衝突・堆積プロセスであるウォームスプレーにより、光電変換材料TiO_2と電子貯蔵材料Fe_2O_3からなるナノサイズ酸化物に金属亜鉛を添加した原料粉末を用いてコンポジットコーティングを作製した。コーティングの堆積機構および光カソード防食特性について種々の分析・評価を行った。
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渡辺 豊, 杉森 健太
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釜谷 昌幸, 板倉 充洋
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In this study, initiation and growth of intergranular stress corrosion cracking was evaluated by a Monte Carlo simulation. A three-dimensional polycrystalline body was generated by Voronoi tessellation. The effect of stress concentration around pre-existing cracks was taken into account by applying the finite element method. Initiation and propagation of the cracks were modeled based on concepts of damage mechanics. The simulation could reproduce cracking behavior observed in the experiment. Increase in number of cracks was saturated and was followed by decrease as experimentally observed. This caused by preferential crack initiation at the stress-concentration zones and suppression of crack initiation in stress-shielding zones. It was concluded that the local stress brought about by pre-existing cracks plays an important role in the initiation and growth of cracks, and the simulation could imitate the cracking behavior under interaction.
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水谷 義弘, 黛 正己
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The purpose of this study is to clarify the effect to SCC growth evaluation, when deleting the lower shelf of the SCC growth rate curves used for FFS. Numerical calculation was conducted for 600A piping, and found that this deleting is less effected to the growth evaluation. Moreover, for such piping, cracks are considered to be stopped in the middle of thickness regardless of initial crack size or crack growth rate curves. Therefore, when the residual stress becomes negative before required wall thickness, it is thought that SCC growth evaluation should not necessary.
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呂 戦鵬, 竹田 陽一, 根岸 孝次, 伊藤 譲, 庄子 哲雄
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The effect of dissolved oxygen (DO) content and the resultant electrochemical potential on the stress corrosion cracking growth rate of 316L weld metals in simulated boiling water reactor environments was investigated by using fracture mechanics specimens and in-situ crack growth monitoring. The fracture surfaces show extensive interdendritic stress corrosion characteristics. The crack growth rate in 2ppm DO water is significantly higher that in 0.2ppm DO water. The effect of higher DO concentrations such as 7.5ppm or 11ppm on crack growth rate are different for 316L weld metals with different ferrite contents.
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岡島 智史, 泉 聡志, 酒井 信介
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The evaluation method for the pipe integrity in the form of failure probability has been developed based on the Bayesian inference method in the previous paper, in this paper, the previous method is extended for the wall-thinning model with the fluctuation of corrosion influence factors. The extension is carried out through following two approaches: correction-term and error-term approaches. After the formulation is shown, validity of the evaluated failure probability is examined.
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巨 陽
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A method which can inspect a pipe in a large scale and measure the wall thinning remotely was demonstrated. A copper pipe having 17 mm inner diameter, 1 mm wall thickness, and 900 mm length was measured. The thickness reduction having the value from 10% to 80% of the wall thickness was detected significantly. By building up a resonance for the microwave signal propagated in the pipe, it is possible to determine the wall thinning using the measured resonance frequency.
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渡邊 壮太, 上野 知洋, 高橋 宏治, 安藤 柱
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Cyclic bending tests were conducted using elbow pipe specimens with local wall thinning. Local wall thinning was machined on the inside of pipe in order to simulate erosion/corrosion metal loss. The effects of thinned locations on the failure behaviors of the pipes were investigated. As a result, when the wall thinning was located in intrados, fatigue life was the shortest. In addition, three-dimensional elasto-plastic analyses were also carried out using the finite element method. The analyses were carried out focusing on Mises' total strain range. As the results, the location of crack initiation and the crack growth direction were successfully predicted by the analyses. The fatigue life was predicted on the safe side by the Manson's universal slope method.
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原 拓巳, 角井 聖, 高田 一, 三上 晃
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三浦 直樹, 町田 秀夫
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Surface cracked plates are typical structure elements with postulated cracks. Accurate calculation of stress intensity factors for cracked plates subjected to arbitral stress distribution is essential to predict the crack growth behavior due to fatigue or SCC. Some stress intensity factor solutions for cracked plates have been proposed so far. In this paper, these solutions were compared each other from the viewpoint of the applicability to actual plant components, and a solution was selected which could be suitable for codification.
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青池 聡, 根布 景, 設楽 親, 中川 雄介
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Evaluation methods of stress intensity factor for a surface crack in finite width plate attached to inclined thick plate were tested by FEM analyses and fatigue crack growth tests. The influence of crack depth and crack width on stress intensity factor was studied. From these tests following results were obtained. When a/t ratio equaled 0.5 or less and c/W ratio equaled 0.7 or less, stress intensity factor for a surface crack in finite width plate attached to inclined thick plate was evaluated conservative because of applying the function of finite width correction that had studied by Newman and Raju to an influence function method for flat plates with a surface crack.
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小川 和夫, 齋藤 利之, 板谷 雅雄
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Stress corrosion cracking (SCC) in the weld joint of Ni-base alloy occurs in Japanese and foreign nuclear power plants. In applying fracture mechanics it is important to clarify the SCC crack that propagates by various factors for the reliability of the aged plants. In this study, axial surface cracks are assumed to the weld metal of weld H-11 in BWR shroud support structure. And arbitrary loads are given to the surface crack and stress intensity factor K is calculated by the FEM analysis. The coverage of the crack configuration provided for by Rules on Fitness-for-Service for Nuclear Power Plants and the engineering effectiveness of the K solution for plate are examined.
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小川 和夫, 宮崎 克雅, 斎藤 高一
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It is important to clarify the effect of geometry, such as vessel penetration nozzle installation on stress intensity factor (SIF) for the SCC growth evaluation. This paper shows the non-axisymmetric effect on the SIFs of surface flaw located at in-core monitor (ICM) housing in Boiling Water Reactor, by comparing SIFs in uphill or downhill side of outer nozzle and central nozzle. The difference of SIFs in the oblique nozzle from axisymmetric nozzle is larger with the circumferential flaw being deeper. Furthermore, K estimated by FEA and simplified solutions in JSME Code were compared to confirm the applicability of the simplified solutions to the vessel penetration nozzle. The stress intensity factor for ICM housing could be estimated by using the simplified solutions for pipe, conservatively.
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小川 和夫, 室屋 格, 北条 公伸, 越智 真弓
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The evaluation procedure of stress intensity factor (SIF) for stress corrosion cracking (SCC) of Ni-base alloys was developed. Since SCC grows only in the alloys, the existing SIF equation for semi-elliptical surface cracks tends to over-estimate the SIF for deep longitudinal crack in pipe welds. The crack is modeled as rectangular crack, and it is confirmed that the SIF equation developed gives reasonable estimation results.
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板谷 雅雄, 小川 和夫, 齋藤 利之, 林 貴広, 楢崎 千尋
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Stress corrosion cracking (SCC) in the weld joints of Ni-base alloys in BWR plants has been reported and is one of the most important issues in the structural integrity assessment of the Ni-base alloy weld components. In the structural integrity evaluation, based on the fracture mechanics, the modeling of the crack shape is important. In this study, stress intensity factor K of axial surface cracks with elliptical and trapezoidal shapes in the weld metal in the BWR shroud support joints were evaluated by FEM analysis in order to examine the applicability of elliptical surface crack model that is generally adopted in the codes and standards to the stress intensity factor evaluation of trapezoidal surface crack.
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町田 秀夫, 波木井 順一, 高橋 嘉明
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This paper describes the study on application of partial safety factor for design and maintenance of nuclear power plant facilities. The trend to utilize risk information is activating for the rational design and the maintenance of nuclear power plant facilities. In this study, risk information is assumed as the reliability of components, and the partial safety factor (PSF) for satisfying this requirement was evaluated using Load and Resistance Factor Design method (LRFD). This result suggests that it is possible to rationalize the safety factors defined in conventional Design and Construction Code and Fitness-for-Service Code.
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鬼沢 邦雄
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三輪 幸夫, 加治 芳行, 大久保 成彰, 近藤 啓悦, 塚田 隆
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In core structural materials of next generation reactors such as a liquid-metal cooled fast breeding reactor and a supercritical-water cooled thermal or first reactor, materials' degradation behavior by neutron irradiation damage and thermal (cyclic) stress should be considered with fair accuracy in design process (including maintenance and repair plans), because the materials are used under higher temperature gradients and higher neutron flux fields than those in the present light water reactors. In the current experiential design rules, service lives of core structural components were determined by the materials degradation such as the increase of ductile-to-brittle transition temperature after post irradiation examination data. However, other materials degradations such as irradiation-assisted stress corrosion cracking (IASCC), which occurs by the degradation synergistically interacting with radiation hardening, local chemical composition change, swelling and radiation creep, should be considered reasonably in the design process of the next generation reactors, because of the anticipation of the beneficial effects by synergy of radiation damage. The radiation hardening and local chemical composition change at grain boundaries due to radiation-induced segregation increased with increasing dose. Above some threshold dose, swelling increased rapidly with increasing dose. Residual stress due to thermal stress and welding procedure decreased with increasing dose. To predict material failure by IASCC with reasonable accuracy, in this study, each material degradation phenomenon with different dose dependence was modeled with consideration of radiation induced stress relaxation. And then the models were integrated to simulate the failure behavior for the duration of reactor operation period. In this paper, the models obtained by ion-irradiation experiments and compared by data from neutron irradiation experiments were presented, and the concept of our new evaluation method and the programming code for the failure simulation were outlined.
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鈴木 一彦, 實川 資朗
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A new, systematic concept of structural integrity assurance is proposed for application to components with reducing or reduced ductility materials. The current structural codes are all based on the assumption of no significant changes in mechanical property in service and high ductility. Intense neutron irradiation at moderate temperatures in nuclear reactors and fusion machines, for example, induces hardening, e.g., a significant change in yield strength, and then reduction in ductility. Therefore, failure modes to be prevented are discussed, first, for components with such materials. Second, a new concept of limiting strength is proposed. Then, a systematic concept of ductile fracture prevention is proposed, by reasonably applying loading type-depending limiting strengths.
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鈴木 一彦, 大久保 成彰, 實川 資朗
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A systematic criterion on ductile fracture is proposed for metallic materials with not only a high ductility but also a reducing ductility under intense neutron irradiation or under other environments, because a ductile fracture strength is a key limiting strength for assuring the structural integrity of reducing ductility components. To develop the criterion, a true stress-true strain correlation (a constitutive equation) shall be formulated over the strain range to fracture. When a significant hardening, typically a drastic increase in yield strength, is caused by neutron irradiation or by cold rolling, Swift's equation is found to suitably correlate experimental data on stress-strain curves, by adjusting a prestrain ε_0 to the hardening effects. Concerning the ductile fracture criterion, it is not easy to develop that, because the ductile fracture mechanism is very complicated. The authors show that the fracture condition is approximated reasonably on the safe side by a condition on onset of local necking, and then propose the fracture criterion.
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西田 秀高
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Damage for Welding Fine HAZ Parts of Boiler Piping (Type N Damage) loaded internal and bending Force at one time is needs High Accuracy Residual Life Assesment, but can't clear that's Mechanism now. So for the purpose of Deveropment of High Accuracy Residual Life Assesment, we developed of burst equipment that simulated actual Boiler size for welding parts of Boiler Piping of re-created Type IV Damage of Serviced Boiler at first time in Japan. For Three Years ( About Twenty thousands Hours), The Effect of loading Internal and Bending Force at one time. The cracks generate from Welding Fine HAZ Parts and Welding Parts of Boiler Piping and Its Piping was burst. We succeeded to re-create Burst Circumstance of Serviced Boiler.
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板谷 雅雄, 金澤 寧, 田中 徳彦, 設楽 親, 中川 雄介
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Fracture assessment method for piping of BWR reactor internal with circumferential crack is described in JSME Code, Rules on Fitness-for-Service for Nuclear Power Plants 2004 Edition. In this code, limit load is calculated assuming a/t=1 for through wall crack. It has been expected to demonstrate the adequacy of this equation experimentally. Furthermore, the crack plane in weld HAZ of core spray sparger between header and pipe is not straight and has some curvature. The fracture tests were conducted for pipe with circumferential through wall crack between header and pipe to demonstrate the applicability of current JSME method. Limit load analyses by FEM were also conducted. It was confirmed that the limit load equation in the current JSME Code is possible to apply to the pipe with circumferential through wall crack even if the crack plane was curved along the weld between header and sparger pipe.
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小川 和夫, 柳田 信義, 斎藤 高一
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Residual stress distribution in an oblique nozzle jointed to the vessel by J-groove welds was analyzed using three-dimensional finite element method. All of welding passes were considered in a one-half symmetry FE model. And temperature and stress were modeled for simultaneous bead laying. The analytical result shows good agreement with the experimental measurement data, indicating that the FE modeling is valid.
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田中 良彦, 高木 愛夫, 鈴木 俊一
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大熊 俊司, 小川 和夫, 内田 憲, 齋藤 利之
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Steady state Eulerian analysis on thermal simulation of welds using moving coordinates is known as a very computationally efficient method. This paper presents steady state Eulerian thermal analysis that is applied for the BWR shroud support weld joints H8 and H9. In this analysis, model parameters of heat inputs are defined by only welding condition and material properties, therefore, no calibration with measured data required. Comparison between the analyzed temperature histories and the measured experimental results of BWR shroud support weld joints H8 and H9 shows that the numerical results reproduce the measured results well. From this study, by applying the steady state Eulerian thermal analysis with conventional stress analysis, it is shown that welding temperature histories can be estimated without mockup experiments for heat input calibration.
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都井 裕, 高垣 昌和, 広瀬 智史, 高橋 由紀夫
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寺前 哲夫
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中谷 祐二郎, 田中 明, 石渡 裕, 野口 裕久, 只野 裕一
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川内 英史, 鈴木 謙一
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Since the age-related degradation of structures and components in NPPs has been a key issue regarding assessments of seismic safety, JNES initiated seismic test programs in fiscal 2004 for the degraded core shroud used in old BWR plants. The objectives were to: i) obtain a better understanding of the vibration characteristics and seismic strength of degraded structures and components having cracks due to aging, ii) ensure a margin of seismic design safety by considering age-related cracking, and iii) verify the JSME Code Rules on Fitness-for-Service for NPPs in Japan. The monotonic and cyclic loading tests of shroud shell and support element models were conducted. The shaking tests of the 1/2.5 scale shroud model were performed on the shaking table. All test models were designed to contain simulated cracking due to aging, involving cracks assumed to have the maximum allowable size according to the JSME Code Rules. This paper reports on the summary of these test results by focusing on vibration characteristics, seismic strength and a seismic design safety margin of the JSME rules.
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川内 英史, 鈴木 謙一
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Since the age-related degradation of structures and components in NPPs has been a key issue regarding assessments of seismic safety, JNES initiated seismic test programs in fiscal 2004 for the degraded core shroud used in old BWR plants. The objectives were to: i) obtain a better understanding of the vibration characteristics and seismic strength of degraded structures and components having cracks due to aging, ii) ensure a margin of seismic design safety by considering age-related cracking, and iii) verify the JSME Code Rules on Fitness-for-Service for NPPs in Japan. The monotonic and cyclic loading tests of piping element models were conducted. The shaking tests of the about 1/3 scale PLR piping system model were performed on the shaking table. All test models were designed to contain simulated cracking due to aging, involving cracks assumed to have the maximum allowable size according to the JSME Code Rules. This paper reports on the summary of these test results by focusing on vibration characteristics, seismic strength and a seismic design safety margin of the JSME rules.
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岡島 智史, 本田 圭, 酒井 信介, 泉 聡志, 大石 邦央, 笠原 直人
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It is well known that fatigue damage accumulates around T-junctions of piping system where two kinds of fluid with different temperatures are mixed. Kasahara et al. have proposed the thermal fatigue evaluation method based on power spectrum density(PSD). However, this method is too complex to practical use in the design stage. In this paper, a simplified damage evaluation guideline is proposed based on the Kasahara et al. method. The damage evaluation procedure from stress PSD is simplified in this guideline.
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高橋 文雄, 丹下 彰, 小野 芳樹, 安藤 柱
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宮崎 裕司, 高橋 宏治, 安藤 柱
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In the previous study on pipe with wall thinning, wall thinning part has been assumed as smooth. Therefore the effects of multi surface pits which occurred in the wall thinning part on low cycle fatigue strength of pipes are not clarified. In this study, plane bending fatigue test was performed using the specimen having multi surface pits and their effects on low cycle fatigue strength for pipes were evaluated. Consequently, it was found that the effect of pits on the number of cycle to failure(N_f) was small when N_f was less than 10^3. The universal slope method gave a safety evaluation of N_f for specimens having pits.
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松田 昭博, 森井 浩, 矢花 修一
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This paper shows the temperature distribution of a hydraulic generator using the thermograph camera, and thermal aging test results of the rubber seals in the hydraulic generator to extend the overhaul interval. In the temperature observation of the hydraulic generator, the temperature distribution was observed 4 times in a year, and it was forecast that the upper part of the bearing cover of water turbine and the lower part of generator cover were parts where the heat deterioration was promoted most. In thermal aging tests of rubber seal, the permanent strain of rubber seals were evaluated on 90℃, 105℃ and 120℃. The time when the rubber seal shows 80 and 90% permanent strain on 50℃ was estimated as 3.2 and 11.7 years respectively.
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