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Self-Floating Efficient Solar Steam Generators Constructed Using Super-Hydrophilic N,O Dual-Doped Carbon Foams from Waste Polyester 被引量:5
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作者 Huiying Bai Ning Liu +5 位作者 Liang Hao Panpan He Changde Ma Ran Niu Jiang Gong Tao Tang 《Energy & Environmental Materials》 SCIE EI CAS CSCD 2022年第4期1204-1213,共10页
Solar evaporation is recognized as a prospective technique to produce freshwater from non-drinkable water using inexhaustible solar energy.However,it remains a challenge to fabricate low-cost solar evaporators with ob... Solar evaporation is recognized as a prospective technique to produce freshwater from non-drinkable water using inexhaustible solar energy.However,it remains a challenge to fabricate low-cost solar evaporators with obviously reduced water evaporation enthalpy to achieve high evaporation rates.Herein,N,O dual-doped carbon foam(NCF)is fabricated from the lowtemperature carbonization of poly(ethylene terephthalate)(PET)waste by melamine/molten salts at 340℃.During carbonization,melamine reacts with carboxylic acids of PET degradation products to yield a crosslinking network,and then molten salts catalyze the decarboxylation and dehydration to construct a stable framework.Owing to rich N,O-containing groups,3D interconnected pores,super-hydrophilicity,and ultra-low thermal conductivity(0.0599 W m^(−1) K^(−1)),NCF not only achieves high light absorbance(ca.99%)and solar-to-thermal conversion,but also promotes the formation of water cluster to reduce water evaporation enthalpy by ca.37%.Consequently,NCF exhibits a high evaporation rate(2.4 kg m^(−2) h^(−1)),surpassing the-state-of-the-art solar evaporators,and presents good antiacid/basic abilities,long-term salt-resistance,and self-cleaning ability.Importantly,a large-scale NCF-based outdoor solar desalination device is developed to produce freshwater.The daily freshwater production amount per unit area(6.3 kg)meets the two adults’daily water consumption.The trash-to-treasure strategy will give impetus to the development of low-cost,advanced solar evaporators from waste plastics for addressing the global freshwater shortage. 展开更多
关键词 carbon foam solar desalination solar energy solar steam generator waste plastics
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Enhanced photothermal PVA aerogel containing"nut-cake-like"filler consisting of edge oxidized graphene and liquid gallium for efficient solar steam generation
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作者 Xue-Zhong Zhang Die Wu +7 位作者 Yan-Hong Yang Dong Xiang Yan-Lin Zhu Eileen Harkin-Jones Yuan-Peng Wu Qiang Fu Zong-Kai Yan Hua Deng 《Rare Metals》 2025年第6期4038-4049,共12页
A solar steam generator(SSG)is an effective method for solving water shortages and protecting the environment,but its evaporation rate remains limited.Herein,Ga@EOG/PVA aerogel-based SSG with excellent photothermal se... A solar steam generator(SSG)is an effective method for solving water shortages and protecting the environment,but its evaporation rate remains limited.Herein,Ga@EOG/PVA aerogel-based SSG with excellent photothermal seawater purification capabilities was prepared using liquid metal gallium(Ga),edge oxidized graphene(EOG),and polyvinyl alcohol(PVA).The‘‘nut-cake-like''structure formed by electrochemical oxidation of EOG encapsulated Ga nanoparticles enhances light absorption and heat conversion efficiency through multiple light scattering and surface plasmon resonance.Furthermore,the vertical pore structure of the aerogel mimics the xylem conduit in tree trunks,allowing rapid transmission of heat and water,thus increasing its evaporation capacity.Based on these attributes,the SSG demonstrated a light absorption rate of 98.2%and an evaporation rate of 5.13 kg.m^(-2).h^(-1)under one-sun illumination,surpassing previously reported values in the literature.Moreover,the SSG effectively treated heavy metal salts,organic dyes,wastewaters,and acidic or alkaline solutions.These findings highlight the potential effectiveness of the prepared aerogel for numerous of environmental remediation applications,especially in ensuring high water quality and safety for human consumption. 展开更多
关键词 Solar steam generator Edge oxidized graphene Liquid metal gallium Synergistic photothermal Nut-cake-like
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Systematic experimental investigation on pressure build-up characteristics of water-jet injection into a molten LBE pool 被引量:1
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作者 Hao-Ran Huang Zi-Jian Deng +1 位作者 Song-Bai Cheng Jia-Yue Chen 《Nuclear Science and Techniques》 2025年第1期161-174,共14页
In the scenario of a steam generator tube rupture accident in a lead-cooled fast reactor,secondary circuit subcooled water under high pressure is injected into an ordinary-pressure primary vessel,where a molten lead-b... In the scenario of a steam generator tube rupture accident in a lead-cooled fast reactor,secondary circuit subcooled water under high pressure is injected into an ordinary-pressure primary vessel,where a molten lead-based alloy(typically pure lead or lead-bismuth eutectic(LBE))is used as the coolant.To clarify the pressure build-up characteristics under water-jet injection,this study conducted several experiments by injecting pressurized water into a molten LBE pool at Sun Yat-sen University.To obtain a further understanding,several new experimental parameters were adopted,including the melt temperature,water subcooling,injection pressure,injection duration,and nozzle diameter.Through detailed analyses,it was found that the pressure and temperature during the water-melt interaction exhibited a consistent variation trend with our previous water-droplet injection mode LBE experiment.Similarly,the existence of a steam explosion was confirmed,which typically results in a much stronger pressure build-up.For the non-explosion cases,increasing the injection pressure,melt-pool temperature,nozzle diameter,and water subcooling promoted pressure build-up in the melt pool.However,a limited enhancement effect was observed when increasing the injection duration,which may be owing to the continually rising pressure in the interaction vessel or the isolation effect of the generated steam cavity.Regardless of whether a steam explosion occurred,the calculated mechanical and kinetic energy conversion efficiencies of the melt were relatively small(not exceeding 4.1%and 0.7%,respectively).Moreover,the range of the conversion efficiency was similar to that of previous water-droplet experiments,although the upper limit of the jet mode was slightly lower. 展开更多
关键词 Lead-cooled fast reactor steam generator tube rupture accident Pressure build-up characteristics Experimental study Pressure water-jet injection
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An identification model for weak influence parameters of nuclear power unit based on parameter recursion
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作者 LIANG Qian-Yun XU Xin 《四川大学学报(自然科学版)》 北大核心 2025年第4期986-991,共6页
In complex systems,there is a kind of parameters having only a minor impact on the outputs in most cases,but their accurate values are still critical for the operation of systems.In this paper,the authors focus on the... In complex systems,there is a kind of parameters having only a minor impact on the outputs in most cases,but their accurate values are still critical for the operation of systems.In this paper,the authors focus on the identification of these weak influence parameters in the complex systems and propose a identification model based on the parameter recursion.As an application,three parameters of the steam generator are identified,that is,the valve opening,the valve CV value,and the reference water level,in which the valve opening and the reference water level are weak influence parameters under most operating conditions.Numerical simulation results show that,in comparison with the multi-layer perceptron(MLP),the identification error rate is decreased.Actually,the average identification error rate for the valve opening decreases by 0.96%,for the valve CV decreases by 0.002%,and for the reference water level decreases by 12%after one recursion.After two recursions,the average identification error rate for the valve opening decreases by 11.07%,for the valve CV decreases by 2.601%,and for the reference water level decreases by 95.79%.This method can help to improve the control of the steam generator. 展开更多
关键词 steam generator Nuclear power Parameter identification Multi-layer perceptron
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Phase behavior evolution in the interaction of lead-bismuth liquid metal and water
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作者 Lin Zhang Chang Deng +2 位作者 Guang-Chao Yang Hui He Xiao-Jing Liu 《Nuclear Science and Techniques》 2025年第11期353-365,共13页
The vapor diffusion and transport resulting from steam generator tube rupture(SGTR)accidents are a major concern threatening lead-based reactor core safety.In this study,a high-parameter SGTR experimental platform and... The vapor diffusion and transport resulting from steam generator tube rupture(SGTR)accidents are a major concern threatening lead-based reactor core safety.In this study,a high-parameter SGTR experimental platform and the multi-phase multi-physics processes numerical simulation were developed to investigate the phase behavior and interaction mechanisms.This study revealed the interaction mechanisms of lead-bismuth liquid metal and water driven by flash vaporization,jet impingement boiling,and moderate boiling.The migration and evolution of the discrete phases(vapor-water mixture)were inferred from the temperature transient laws and a numerical simulation.The results revealed that the evolution of the discrete phases consists of three stages:cavity formation,flanking diffusion,and stable up-floating.The jet pressure significantly extended the disturbance period.Variations in the water temperature mainly affected the depressurization boiling process,altering the diffusion region of the discrete phases.The temperature of the liquid metal and the duration of the jet had a minimal impact on the behavior of the discrete phases.This study provides a crucial reference for constructing a complete picture of accident evolution. 展开更多
关键词 Discrete phases migration LBE-water interaction steam generator tube rupture Lead-cooled fast reactors
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CFD analysis of a CiADS fuel assembly during the steam generator tube rupture accident based on the LBEsteamEulerFoam 被引量:4
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作者 Yun-Xiang Li Lu Meng +8 位作者 Song Li Zi-Nan Huang Di-Si Wang Bo Liu You-Peng Zhang Tian-Ji Peng Lu Zhang Xing-Kang Su Wei Jiang 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第10期136-147,共12页
Steam generator tube rupture(SGTR) accident is an important scenario needed to be considered in the safety analysis of lead-based fast reactors. When the steam generator tube breaks close to the main pump, water vapor... Steam generator tube rupture(SGTR) accident is an important scenario needed to be considered in the safety analysis of lead-based fast reactors. When the steam generator tube breaks close to the main pump, water vapor will enter the reactor core, resulting in a two-phase flow of heavy liquid metal and water vapor in fuel assemblies. The thermal-hydraulic problems caused by the SGTR accident may seriously threaten reactor core's safety performance. In this paper, the open-source CFD calculation software OpenFOAM was used to encapsulate the improved Euler method into the self-developed solver LBEsteamEulerFoam. By changing different heating boundary conditions and inlet coolant types, the two-phase flow in the fuel assembly with different inlet gas content was simulated under various accident conditions. The calculation results show that the water vapor may accumulate in edge and corner channels. With the increase in inlet water vapor content, outlet coolant velocity increases gradually. When the inlet water vapor content is more than 15%, the outlet coolant temperature rises sharply with strong temperature fluctuation. When the inlet water vapor content is in the range of 5–20%, the upper part of the fuel assembly will gradually accumulate to form large bubbles. Compared with the VOF method, Euler method has higher computational efficiency. However, Euler method may cause an underestimation of the void fraction, so it still needs to be calibrated with future experimental data of the two-phase flow in fuel assembly. 展开更多
关键词 steam generator tube rupture CiADS CFD simulations Two-phase flow
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Correlation Dimension in Fault Diagnosis of 600 MW Steam Turbine Generator 被引量:2
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作者 姚宝恒 杨霞菊 +1 位作者 佟德纯 陈兆能 《Journal of Donghua University(English Edition)》 EI CAS 2005年第1期31-36,共6页
GP algorithm of correlation dimension computation is ameliorated which overcomes the shortage of traditional one. Improved process of GP algorithm takes the influence of temporal correlative pairs of points on correla... GP algorithm of correlation dimension computation is ameliorated which overcomes the shortage of traditional one. Improved process of GP algorithm takes the influence of temporal correlative pairs of points on correlation dimension into account and promotes the computational efficiency prominently. Iterative SVD method is applied to remove the influence of noise on the result of correlation dimension. The faults of steam flow turbulence and oil film disturbance which occur in 600 MW Steam Turbine Generator are analyzed and whose correlation dimensions are computed. More distinct quantitative index than FFT is gained to distinguish two faults and it’s of little importance to apply correlation dimension to study the influence of various factors on steam flow turbulence fault for nonexistence of convergent floor in correlation integral curve, which presents a new way to learn the operational function of large capacity steam turbine generator and carry out comprehensive condition monitoring. 展开更多
关键词 correlation dimension ameliorated algorithm 600 MW steam turbine generator air turbulence oil film disturbance.
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Transient Analysis of Steam Generator in PWR Nuclear Power Plant 被引量:1
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作者 M.Tahir Khaleeq Lang Wengpeng He Guoseng (School of Automation) 《Advances in Manufacturing》 SCIE CAS 1998年第2期43-50,共8页
The water level control system of steam generator in a pressurized water reactor of nuchear power plant plays an important role which effects the water level control of the steam generator are due the reverse dynamics... The water level control system of steam generator in a pressurized water reactor of nuchear power plant plays an important role which effects the water level control of the steam generator are due the reverse dynamics behavior,so the transient analysis of the steam generator should firstly solve their mathematical models.For determination of dynamic behavior and design and testing of the control system, a nonlinear math model is developed using one dimensional conservation equations of mass,momentum and energy of primary and secondary sides of the steam generator. The nonlinear model is verified with standard power plant data available in the references, then the steady states and transient calculations are performed for full power to 5% power reactor operation of the steam generator of Chinese Qinshan Nuclear Power Plant. 展开更多
关键词 nuclear power plant steam generator nonlinear mathematical model qinshan nuclear powerplant
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A Novel Computerized Water Level Control System of PWR Steam Generator of Nuclear Power Plant 被引量:1
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作者 M.Tahir Khaleeq Lang Wenpen He Guosen (School of Automation) 《Advances in Manufacturing》 SCIE CAS 1998年第3期56-66,共11页
This paper presents a novel method to solve old problem of water level control system of pressurized water reactor (PWR) steam generator (SG) of nuclear power plant (NPP) .The level control system of SG plays an impo... This paper presents a novel method to solve old problem of water level control system of pressurized water reactor (PWR) steam generator (SG) of nuclear power plant (NPP) .The level control system of SG plays an important role which effects the reliablity,safty,cost of SG and its mathematical models have been solved.A model of the conventional controller is presented and the existing problems are discussed. A novel rule based realtime control technique is designed with a computerized water level control (CWLC) system for SG of PWR NPP.The performance of this is evaluated for full power reactor operating conditions by applying different transient conditions of SG′s data of Qinshan Nuclear Power Plant (QNPP). 展开更多
关键词 steam Generator (SG) Pressurized Water Reactor (PWR) Nuclaer Power Plant (NPP) Rule based Real time Control (RRC)
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Dynamic simulation of drum level sloshing of heat recovery steam generator
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作者 曹小玲 皮正仁 +2 位作者 蒋绍坚 杨卫宏 B.Wlodzimerz 《Journal of Central South University》 SCIE EI CAS 2013年第2期413-423,共11页
Drum level sloshing is the latest discovery in the application of heat recovery steam generator (HRSG) in combined cycle, and shows certain negative influence on drum level controlling. In order to improve drum level ... Drum level sloshing is the latest discovery in the application of heat recovery steam generator (HRSG) in combined cycle, and shows certain negative influence on drum level controlling. In order to improve drum level controlling, influence factors on the drum level sloshing were investigated. Firstly, drum sub-modules were developed using the method of modularization modeling, and then the model of drum level sloshing was set up as well. Experiments were carried out on the experimental rig, and the model was validated using the obtained experimental results. Dynamic simulation was made based on the model to get a 3-D graph of drum level sloshing, which shows a vivid procedure of drum level sloshing. The effect of feed-water flow rate, main-steam flow rate and heating quantity on the drum level sloshing was analyzed. The simulation results indicate that the signals with frequency higher than 0.05 Hz are that of drum level sloshing, the signals with frequency of 0.0-0.05 Hz are that of drum level trendy and "false water level", and variation of the feed-water flow rates, main-steam flow rates and heating quantities can change the frequency of drum level sloshing, i.e., the frequency of sloshing increases with the increase of feed-water flow rate, or the decrease of the main-steam flow rate and the heating quantity. This research work is fundamental to improve signal-to-noise ratio of drum level signal and precise controlling of drum level. 展开更多
关键词 combined cycle heat recovery steam generator false level drum level sloshing model modularization modeling
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Modeling a high output marine steam generator feedwater control system which uses parallel turbine-driven feed pumps
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作者 邱志强 邹海 孙建华 《Journal of Marine Science and Application》 2008年第3期212-217,共6页
Parallel turbine-driven feedwater pumps are needed when ships travel at high speed. In order to study marine steam generator feedwater control systems which use parallel turbine-driven feed pumps, a mathematical model... Parallel turbine-driven feedwater pumps are needed when ships travel at high speed. In order to study marine steam generator feedwater control systems which use parallel turbine-driven feed pumps, a mathematical model of marine steam generator feedwater control system was developed which includes mathematical models of two steam generators and parallel turbine-driven feed pumps as well as mathematical models of feedwater pipes and feed regulating valves. The operating condition points of the parallel ttu-bine-driven feed pumps were calculated by the Chebyshev curve fit method. A water level controller for the steam generator and a rotary speed controller for the turbine-driven feed pumps were also included in the model. The accuracy of the mathematical models and their controllers was verified by comparing their results with those from a simulator. 展开更多
关键词 feedwater control steam generator MODELING feed pump TURBINE
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Simulation analysis of static and dynamic characteristics of once-through steam generator in concentric annuli tube
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作者 ZHANG Wei BIAN Xin-qian XIA Guo-qing 《Journal of Marine Science and Application》 2006年第3期36-40,共5页
The once-through steam generator (OTSG) in concentric annuli tube is a new type of steam generator which applies double side to transfer heat. The heat flux between the water of centric tube, outside annuli tube and t... The once-through steam generator (OTSG) in concentric annuli tube is a new type of steam generator which applies double side to transfer heat. The heat flux between the water of centric tube, outside annuli tube and that of annulus channel is assumed to be equal, and then the steam generator’s model is built by lumped parameters with moving boundary. In the basis of the built model, static and dynamic characteristics are analyzed. The static characteristics are proved by experiment results in a 19-tube once-through steam generator of Babcock & Wilcox. The characteristics that the lengths of three regions (subcooled region, nucleate boiling region, superheat region) change with power can be explained by theory analysis. The dynamic characteristics accord with the heat and hydraulics and the results of analysis according to the mechanism. 展开更多
关键词 once-through steam generator dynamic characteristics simulatin CALCULATION
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Scaling Analysis of Thermal-Hydraulics for Steam Generator Passive Heat Removal System
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作者 周源 林萌 +1 位作者 陈金波 王汉林 《Journal of Shanghai Jiaotong university(Science)》 EI 2014年第2期219-225,共7页
Steam generator passive heat removal system(SG-PHRS) is used as a passively safe mode to provide decay heat removal in some advanced pressurized water reactors. Due to the structure characteristics of steam generator(... Steam generator passive heat removal system(SG-PHRS) is used as a passively safe mode to provide decay heat removal in some advanced pressurized water reactors. Due to the structure characteristics of steam generator(SG), there are two natural circulation loops coupling in SG-PHRS in case of a safety-related event. The existing natural circulation scaling criteria could be used to simulate the natural circulation inside SG. Two-phase natural circulation loop is studied carefully, and the dominant effects of SG on behaviors of natural circulation in passive heat removal system are presented. Based on the understanding of SG-PHRS operation, system pressure transient scaling and two-phase natural circulation scaling are analyzed by establishing the relevant continuity,integral momentum and energy equations in one-dimensional area-averaged forms. With modified equations,similarity criteria for SG-PHRS are obtained for engineering application. In addition, equal height simulation and reduced height simulation are studied. 展开更多
关键词 steam generator natural circulation scaling simulation thermal hydraulics
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Simultaneous Solar-driven Steam and Electricity Generation by Cost-effective,Easy Scale-up MnO 2-based Flexible Membranes
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作者 Jiaxin Ren Yang Ding +2 位作者 Jiang Gong Jinping Qu Ran Niu 《Energy & Environmental Materials》 SCIE EI CAS CSCD 2023年第3期184-192,共9页
Harvesting solar energy in an effective manner for steam and electricity generation is a promising technique to simultaneously cope with the energy and water crises.However,the construction of efficient and easy scale... Harvesting solar energy in an effective manner for steam and electricity generation is a promising technique to simultaneously cope with the energy and water crises.However,the construction of efficient and easy scale-up photothermal materials for steam and electricity cogeneration remains challenging.Herein,we report a facile and cost-effective strategy to prepare MnO_(2)-decorated cotton cloth(MCx).The wide adsorption spectrum and excellent photothermal conversion ability of the in situ-formed MnO_(2)nanoparticles make the MCx to be advanced photothermal materials.Consequently,the hybrid device integrated with MCx as the photothermal layer and the thermoelectric(TE)module for electricity power conversion exhibits an extremely high evaporation rate of 2.24 kg m^(−2)h^(−1)under 1 kW m^(−2)irradiation,which is ranked among the most powerful solar evaporators.More importantly,during solar evaporation,the hybrid device produces an open-circuit voltage of 0.3 V and a power output of 1.6 W m^(−2)under 3 Sun irradiation,and outperforms most of the previously reported solar-driven electricity generation devices.Therefore,the integrated device with synergistic solar-thermal utilization opens up a green way toward simultaneous solar vapor and electric power generation in remote and resource-constrained areas. 展开更多
关键词 photothermal material solar desalination solar energy solar steam generator THERMOELECTRICS
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Verification of Integrity of Steam Generator Tubes by Pressure Testing
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作者 Yong-Seok Kang Min-Woo Nam Jai-Hak Park 《Journal of Energy and Power Engineering》 2013年第12期2249-2255,共7页
This paper assessed the benefit of the in-situ pressure test to support steam generator tube integrity assessment and reviewed a conservatism of currently applied structural integrity assessment methodology against de... This paper assessed the benefit of the in-situ pressure test to support steam generator tube integrity assessment and reviewed a conservatism of currently applied structural integrity assessment methodology against defected tubes. According to the steam generator program requirement, condition monitoring assessment was performed to the all detected flaws. For condition monitoring assessments, the limiting structural integrity requirement should be demonstrated for all detected degraded tubes at a probability of at least 0.95 at 50% confidence. Some flaws were slightly exceeded the structural integrity threshold values of the condition monitoring performance limits using analytical method. As a direct evaluation of tube integrity with degraded tubes, in-situ pressure testing performed on some selected flaws and passed all proof and leakage test criteria with no leakage. From this pressure testing, the authors have verified that degraded tubes met a specified value containing a defined safety margins. Also, the authors have confirmed that existing structural assessment methodology has enough margins to retain integrity of steam generator tubes. 展开更多
关键词 Pressure testing steam generator tube integrity assessment.
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Prediction of External Exposure during Dismantling of Steam Generator
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作者 Martin Hornacek Vladimir Necas 《World Journal of Engineering and Technology》 2015年第3期155-162,共8页
The decommissioning of nuclear power plants is in the Slovak Republic an actual issue. In 2015 started the second decommissioning stage of nuclear power plant V1 in Jaslovské Bohunice. This stage involves the dis... The decommissioning of nuclear power plants is in the Slovak Republic an actual issue. In 2015 started the second decommissioning stage of nuclear power plant V1 in Jaslovské Bohunice. This stage involves the dismantling and segmentation of activated (reactor pressure vessel, reactor internals) and contaminated parts (steam generators, pressurizer). From this reason it is necessary to investigate the radiation situation in the vicinity of the component to be cut. The presented results show that during remote dismantling the exposure is small (compared with the fragmentation tasks). Moreover, when the pre-dismantling decontamination with decontamination factor of 100 is applied, the total collective effective dose is below the yearly limit of 20 mSv for workers. 展开更多
关键词 steam Generator Dismantling and Fragmentation External Exposure
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Fretting wear behavior of Inconel 690 in hydrazine environments 被引量:2
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作者 张晓宇 任平弟 +1 位作者 彭金方 朱旻昊 《Transactions of Nonferrous Metals Society of China》 SCIE EI CAS CSCD 2014年第2期360-367,共8页
The friction and wear behaviors of Inconel 690 flat against Si3Ni4 ball were investigated using a hydraulic fretting test rig equipped with a liquid container device. The loads of 20-80 N, reciprocating amplitudes of ... The friction and wear behaviors of Inconel 690 flat against Si3Ni4 ball were investigated using a hydraulic fretting test rig equipped with a liquid container device. The loads of 20-80 N, reciprocating amplitudes of 80-200 μm and two different environments (distilled water and hydrazine solution at temperatures from 25 to 90 ℃) were selected. The results show that the ratio of Ft/Fn is lower in distilled water than that in hydrazine solution at the same temperature in the slip regime. Both the ratio of Ft/Fn and wear volume gradually increase with increasing medium temperature under the given normal load and displacement amplitude. Besides the displacement amplitude and load, temperature also plays an important role for wear behavior of Inconel 690 material. The increase of temperature could reduce the concentration of dissolved oxygen, and promote the absorption reaction of hydrazine and dissolved oxygen. As a result, the oxidative corrosion rate is obviously lowered. Abrasive wear and delamination wear are the main mechanisms of Inconel 690 in distilled water. However, in hydrazine solution the cracks accompanied by abrasive wear and delamination wear are the main mechanisms. 展开更多
关键词 fretting wear steam generator delamination wear
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Passivity Degradation of Nuclear Materials in Reduced Sulfur Environments:A Review 被引量:2
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作者 高志明 王泽清 +4 位作者 孙颖昊 吴思博 马超 祝钰 夏大海 《Transactions of Tianjin University》 EI CAS 2016年第3期189-201,共13页
This paper reviews sulfur-induced passivity degradation of nuclear materials with emphasis on steam generator(SG)alloys. The state of arts on this topic concerning thermodynamic calculation and experimental data has b... This paper reviews sulfur-induced passivity degradation of nuclear materials with emphasis on steam generator(SG)alloys. The state of arts on this topic concerning thermodynamic calculation and experimental data has been reviewed. Thermodynamic calculation results indicate that the distribution of sulfur species strongly depends on p H and temperature. Experimental data show that solution p H, temperature and solution chemistries can significantly affect the electrochemical behaviors of SG materials and the underlying degradation mechanisms. Some issues when conducting corrosion tests at high temperature should be paid attention to, such as the dissolution of the autoclave, which may affect the facticity of the experimental results. 展开更多
关键词 nuclear materials steam generator SULFUR passivity degradation mechanism high temperature
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Experimental investigation on pressure-buildup characteristics of a water lump immerged in a molten lead pool 被引量:2
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作者 Zi-Jian Deng Song-Bai Cheng Hui Cheng 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第3期25-39,共15页
Motivated to understand the pressure-buildup characteristics in a circumstance of a water droplet immerged inside a heavy liquid metal pool,which is a key phenomenon during a Steam Generator Tube Rupture accident of L... Motivated to understand the pressure-buildup characteristics in a circumstance of a water droplet immerged inside a heavy liquid metal pool,which is a key phenomenon during a Steam Generator Tube Rupture accident of Lead-cooled Fast Reactor,many experiments have been conducted by injecting water lumps into a molten lead pool at Sun Yat-sen University.In order to deepen the understanding of the influence of melt material,this lead experiment was compared with a Lead-Bismuth-Eutectic(LBE)experiment in the literature.For both experiments,a steam explosion occurred in a small part of the experi-mental runs,which generally leads to strengthened pressure buildup.Regarding the non-explosion experimental cases,the impact of all parameters employed in lead experiments(i.e.,water lump volume,water lump shape,molten pool depth,and temperature of water and melt)on the pressure buildup is non-negligible and similar to that in our previous experiments using LBE.Notably,limited pressure buildup with an increase in water lump volume was also observed.A slightly more violent pressure buildup tends to appear in the lead experiments than in the LBE experiments under the same experimental conditions,which may be due to the higher thermal conductivity of lead than of LBE.In a few experimental runs with a relatively low melt temperature close to the melting point of lead,local solidification of liquid lead was observed,restricting pressure buildup.For the lead and LBE experiments,the calculated melt kinetic energy conversion efficiencyηhas a relatively small value(not exceeding 1.6%),and theηvalues have an overall positive correlation with the impulse on the molten pool. 展开更多
关键词 Lead-cooled fast reactor steam generator tube rupture accident Pressure-buildup characteristics Experimental study Melt material
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Application of General Fractal Dimension to Coupling Fault Diagnosis 被引量:1
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作者 XUYu-xiu HOURong-tao 《International Journal of Plant Engineering and Management》 2002年第3期157-162,共6页
This paper presents the coucept of general and sensitive dimension, and also proposes the calculation formula of the general dimension least squares method. By calculating and analyzing the power spectrum and general ... This paper presents the coucept of general and sensitive dimension, and also proposes the calculation formula of the general dimension least squares method. By calculating and analyzing the power spectrum and general dimension from the fault sample, the relationship is achieved between sample status and the general dimension from vibration signals of the equipment so as to provide reference to fault diagnosis. Furthermore, a correlation function of general dimension is proposed, and calculations are carried out for a monitor signal and samples signal. The diagnosis method based on fractal theory is effective through the concrete examples of the steam electric generating set fault diagnosis, and the correlation coefficient of general dimension between a monitor signal and samples signal can improve the accuracy for fault diagnosis. 展开更多
关键词 general dimension steam electric generating set coupling fault fault diagnosis
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