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Increasing the Efficiency and Level of Environmental Safety of Pro-Environmental City Heat Supply Technologies by Low Power Nuclear Plants
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作者 Vladimir Kravchenko Igor Kozlov +3 位作者 Volodymyr Vashchenko Iryna Korduba Andrew Overchenko Serhii Tsybytovskyi 《World Journal of Nuclear Science and Technology》 CAS 2024年第2期107-117,共11页
In connection with the current prospect of decarbonization of coal energy through the use of small nuclear power plants (SNPPs) at existing TPPs as heat sources for heat supply to municipal heating networks, there is ... In connection with the current prospect of decarbonization of coal energy through the use of small nuclear power plants (SNPPs) at existing TPPs as heat sources for heat supply to municipal heating networks, there is a technological need to improve heat supply schemes to increase their environmental friendliness and efficiency. The paper proves the feasibility of using the heat-feeding mode of ASHPs for urban heat supply by heating the network water with steam taken from the turbine. The ratio of electric and thermal power of a “nuclear” combined heat and power plant is given. The advantage of using a heat pump, which provides twice as much electrical power with the same heat output, is established. Taking into account that heat in these modes is supplied with different potential, the energy efficiency was used to compare these options. To increase the heat supply capacity, a scheme with the use of a high-pressure heater in the backpressure mode and with the heating of network water with hot steam was proposed. Heat supply from ASHPs is efficient and environmentally friendly even in the case of significant remoteness of heat consumers. 展开更多
关键词 Low-Capacity nuclear Power plants Environmental Friendliness of the Thermal Power Generation Mode Heat Generation Condensation Mode Heat Supply
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Development and Research of Non⁃Stirring Conveying Device for Waste Resin in Nuclear Power Plant
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作者 Jianfa Li Yongzhen Hua +2 位作者 Mingmei Liu Rui Zhang Taishan Lou 《Journal of Harbin Institute of Technology(New Series)》 CAS 2023年第3期45-59,共15页
Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transp... Blockage in the storage and transportation of waste resin is a difficult problem in the radioactive waste treatment process of nuclear power plants.In this study,in order to solve the problems of unstable resin transport concentration and easy blockage of conveying equipment and pipelines in nuclear power plants in China,a set of non⁃stirring conveying devices is developed,and theoretical calculations,simulation analysis and experimental verification are carried out.By transporting resin using the no stirring conveying device developed in this paper,it is not only to eliminate the risk of blockage and ensure the safety of transportation,but also to adjust the concentration of conveying resin to change the transport efficiency according to the operating conditions.The effective bearing rate of waste resin storage tank can be improved,so that the comprehensive performance of waste resin storage and transportation in nuclear power plants can be greatly improved. 展开更多
关键词 nuclear power plant ion exchange resin TRANSPORTATION no stirring device no blockage
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Recent progress and perspective on batteries made from nuclear waste
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作者 Nirmal Kumar Katiyar Saurav Goel 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第3期1-8,共8页
Sustainable energy sources are an immediate need to cope with the imminent issue of climate change the world is facing today.In particular,the long-lasting miniatured power sources that can supply energy continually t... Sustainable energy sources are an immediate need to cope with the imminent issue of climate change the world is facing today.In particular,the long-lasting miniatured power sources that can supply energy continually to power handheld gadgets,sensors,electronic devices,unmanned airborne vehicles in space and extreme mining are some of the examples where this is an acute need.It is known from basic physics that radioactive materials decay over few years and some nuclear materials have their half-life until thousands of years.The past five decades of research have been spent harnessing the decay energy of the radioactive materials to develop batteries that can last until the radioactive reaction continues.Thus,an emergent opportunity of industrial symbiosis to make use of nuclear waste by using radioactive waste as raw material to develop bat-teries with long shelf life presents a great opportunity for sustainable energy resource development.However,the current canon of research on this topic is scarce.This perspective draws fresh discussions on the topic while highlighting future directions in this wealthy arena of research.Graphical abstract A long-lasting miniaturised nuclear battery utilising 14C radioactive isotope as fuel. 展开更多
关键词 Sustainable energy nuclear waste battery NANO-DIAMOND
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PSA study of the effect of extreme snowfall on a floating nuclear power plant:case study in the Bohai Sea
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作者 Lan‑Xin Gong Qing‑Zhu Liang Chang‑Hong Peng 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第11期212-225,共14页
This study presents a probabilistic safety analysis(PSA)method for the external event of extreme snowfall on a floating nuclear power plant(FNPP)deployed in the Bohai Sea.We utilized the Weibull and Gumbel extreme val... This study presents a probabilistic safety analysis(PSA)method for the external event of extreme snowfall on a floating nuclear power plant(FNPP)deployed in the Bohai Sea.We utilized the Weibull and Gumbel extreme value distributions to fit the collected meteorological data and obtained a hazard curve for the event of an extreme snowfall where the FNPP is located,providing a basis for the frequency of extreme snowfall-initiating events.Our analysis indicates that extreme snowfall primarily affects the ventilation openings of the equipment,leading to the failure of devices such as the diesel generators.Additionally,extreme snowfall can result in a loss of off-site power(LOOP).Therefore,the developed extreme snowfall PSA model is mainly based on the LOOP event tree,considering responses such as snowfall removal by personnel.Our calculations indicate a core damage frequency(CDF)of 1.13×10^(-10) owing to extreme snowfall,which is relatively low.The results of the cut-set analysis indicate that valve failures in the core makeup tank(CMT),passive residual heat removal system(PRS),and in-containment refueling water storage tank(IRWST)significantly contribute to the CDF. 展开更多
关键词 Floating nuclear power plant(FNPP) ACP100 Extreme snow PSA External hazard
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Off-Design Simulation of a CSP Power Plant Integrated with aWaste Heat Recovery System
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作者 T.E.Boukelia A.Bourouis +1 位作者 M.E.Abdesselem M.S.Mecibah 《Energy Engineering》 EI 2023年第11期2449-2467,共19页
Concentrating Solar Power(CSP)plants offer a promising way to generate low-emission energy.However,these plants face challenges such as reduced sunlight during winter and cloudy days,despite being located in high sola... Concentrating Solar Power(CSP)plants offer a promising way to generate low-emission energy.However,these plants face challenges such as reduced sunlight during winter and cloudy days,despite being located in high solar radiation areas.Furthermore,their dispatch capacities and yields can be affected by high electricity consumption,particularly at night.The present work aims to develop an off-design model that evaluates the hourly and annual performances of a parabolic trough power plant(PTPP)equipped with a waste heat recovery system.The study aims to compare the performances of this new layout with those of the conventional Andasol 1 plant,with the aim of assessing the improvements achieved in the new design.Based on the results,it can be concluded that the new layout has increased the annual generated power to almost 183 GWh(an increase of about 7.60% is achieved compared to the Andasol 1 layout that generates 169 GWh annually).Additionally,the proposed installation has achieved an efficiency of 20.55%,which represents a 7.87% increase compared to the previous design(19.05%).The Levelized Cost of Electricity(LCOE)of the new layout has been reduced by more than 5.8% compared to the Andasol 1 plant.Specifically,it has decreased from 13.11 to 12.35 c/kWh.This reduction in LCOE highlights the improved cost-effectiveness of the newlayout,making it amore economically viable option for generating electricity compared to the conventional Andasol 1 plant. 展开更多
关键词 Dispatch capacity organic Rankine cycle parabolic trough solar power plant PERFORMANCES waste heat recovery
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A Preliminary Assessment of the Effect of Urban Waste Pollution in the Korle Lagoon Area of Accra, Ghana, on Nutrition and Growth of Maize (Zea mays L.) Plants
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作者 Eureka Emefa Ahadjie Adomako Dzifa Dellor 《Agricultural Sciences》 2023年第6期843-854,共12页
Disposal of domestic and industrial waste into the Odaw River and Korle Lagoon in Accra, Ghana, has led to pollution of the lagoon and surrounding soils. This study compared the elemental concentrations of heavy metal... Disposal of domestic and industrial waste into the Odaw River and Korle Lagoon in Accra, Ghana, has led to pollution of the lagoon and surrounding soils. This study compared the elemental concentrations of heavy metals (lead and zinc) and essential plant macronutrients (nitrogen, phosphorus and potassium) in soils from the Korle Lagoon Area to those in baseline soils from the University of Ghana Agricultural Farm (UG Farm), also in Accra. A comparative pot experiment, using maize (Zea mays L.) as test plant, was conducted to assess the effect of each soil type on plant growth. Soil samples from the Korle Lagoon Area were significantly higher (P < 0.001) in lead (Pb), zinc (Zn), nitrogen (N) and potassium (K) concentrations than samples from the UG Farm. Mean plant height and mean leaf width of maize plants harvested 7 weeks after planting (WAP) were both significantly higher (P < 0.003) for samples from the Korle Lagoon Area soil compared to those from the UG Farm soil. Higher accumulation of Zn (448.3 ± 45.5) in maize shoot within 3 weeks of planting in the Korle Lagoon Area soil had phytotoxic effects on growth, resulting in shoot growth inhibition and reduced uptake of P and K in 11-week-old plants. The findings indicate that though nutrient enrichment due to sewage disposal into the lagoon may increase crop production, the nutritional quality of the crop produced could be compromised by heavy metal accumulation in the soil and subsequent uptake by the plant. 展开更多
关键词 Korle Lagoon waste Management Soil Contamination plant Nutrition PHYTOTOXICITY
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Problems of Hazardous Waste Storage Facilities in Coal-fired Power Plants and Countermeasures
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作者 Wenqi YUE 《Meteorological and Environmental Research》 CAS 2023年第2期57-60,65,共5页
The hazardous waste produced by coal-fired power plants are large in quantity and variety. It is important for ecological environment protection to properly store hazardous waste in coal-fired power plants. The enviro... The hazardous waste produced by coal-fired power plants are large in quantity and variety. It is important for ecological environment protection to properly store hazardous waste in coal-fired power plants. The environmental management of hazardous waste in coal-fired power plants started late, and there are many problems in the construction and management of their storage facilities. In this paper, taking eight typical coal-fired power plants as examples, the present problems of hazardous waste storage facilities in coal-fired power plants are analyzed, and corresponding countermeasures are put forward to solve the main common problems. 展开更多
关键词 Coal-fired power plants Hazardous waste storage Types of problems COUNTERMEASURES
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SRDAAR-QNPP:a computer code system for the real-time dose assessment of an accident release for Qinshan Nuclear Power Plant 被引量:5
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作者 Hu Erbang Wang Han(China Institute for Radiation Protection, Taiyuan 030006, China) 《Journal of Environmental Sciences》 SCIE EI CAS CSCD 1994年第3期296-309,共14页
SRDAAR-QNPP:acomputercodesystemforthereal-timedoseassessmentofanaccidentreleaseforQinshanNuclearPowerPlantHu... SRDAAR-QNPP:acomputercodesystemforthereal-timedoseassessmentofanaccidentreleaseforQinshanNuclearPowerPlantHuErbang;WangHan(Ch... 展开更多
关键词 real-time DOSE assessment COMPUTER CODE system nuclear power plant accident.
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Study on integrated development and hybrid operation mode of nuclear power plant and pumped-storage power station 被引量:5
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作者 Haizheng Wang Caide Peng 《Global Energy Interconnection》 2019年第4期336-341,共6页
The nuclear power plant is suitable for base-load operation, while the pumped-storage unit mainly gives play to capacity benefit in the electric power system;hence, the integrated development and hybrid operation mode... The nuclear power plant is suitable for base-load operation, while the pumped-storage unit mainly gives play to capacity benefit in the electric power system;hence, the integrated development and hybrid operation mode of the two can better meet the needs of the electric power system. This article first presents an analysis of the necessity and superiority of such mode, then explains its meaning and analyzes the working routes. Finally, it proposes the business modes as follows: low price pumping water electricity plus nuclear power in the near term;nuclear power shifted to pumped storage power participating in market competition in the middle term;and, in the long term, nuclear power shifted to pumped storage power as primary and serving as an electric power system when needed. 展开更多
关键词 nuclear POWER plant Pumped-storage POWER STATION Integrated development HYBRID operation MODES
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Optimization of a dynamic uncertain causality graph for fault diagnosis in nuclear power plant 被引量:2
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作者 Yue Zhao Francesco Di Maio +3 位作者 Enrico Zio Qin Zhang Chun-Ling Dong Jin-Ying Zhang 《Nuclear Science and Techniques》 SCIE CAS CSCD 2017年第3期59-67,共9页
Fault diagnostics is important for safe operation of nuclear power plants(NPPs). In recent years, data-driven approaches have been proposed and implemented to tackle the problem, e.g., neural networks, fuzzy and neuro... Fault diagnostics is important for safe operation of nuclear power plants(NPPs). In recent years, data-driven approaches have been proposed and implemented to tackle the problem, e.g., neural networks, fuzzy and neurofuzzy approaches, support vector machine, K-nearest neighbor classifiers and inference methodologies. Among these methods, dynamic uncertain causality graph(DUCG)has been proved effective in many practical cases. However, the causal graph construction behind the DUCG is complicate and, in many cases, results redundant on the symptoms needed to correctly classify the fault. In this paper, we propose a method to simplify causal graph construction in an automatic way. The method consists in transforming the expert knowledge-based DCUG into a fuzzy decision tree(FDT) by extracting from the DUCG a fuzzy rule base that resumes the used symptoms at the basis of the FDT. Genetic algorithm(GA) is, then, used for the optimization of the FDT, by performing a wrapper search around the FDT: the set of symptoms selected during the iterative search are taken as the best set of symptoms for the diagnosis of the faults that can occur in the system. The effectiveness of the approach is shown with respect to a DUCG model initially built to diagnose 23 faults originally using 262 symptoms of Unit-1 in the Ningde NPP of the China Guangdong Nuclear Power Corporation. The results show that the FDT, with GA-optimized symptoms and diagnosis strategy, can drive the construction of DUCG and lower the computational burden without loss of accuracy in diagnosis. 展开更多
关键词 DYNAMIC UNCERTAIN CAUSALITY GRAPH FAULT diagnosis Classification Fuzzy DECISION tree Genetic algorithm nuclear power plant
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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
NomenclatureAArea(m2)DhHydraulicDiameter(m)EEnergyContent(J)fPressureLossCoeficientαVoidFractionHSpecificEnt... NomenclatureAArea(m2)DhHydraulicDiameter(m)EEnergyContent(J)fPressureLossCoeficientαVoidFractionHSpecificEnthalpy(J/kg)IInert... 展开更多
关键词 nuclear power plant STEAM GENERATOR NONLINEAR MATHEMATICAL model qinshan nuclear powerplant
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A power plant for integrated waste energy recovery from liquid air energy storage and liquefied natural gas 被引量:3
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作者 Tongtong Zhang Xiaohui She Yulong Ding 《Chinese Journal of Chemical Engineering》 SCIE EI CAS CSCD 2021年第6期242-257,共16页
Liquefied natural gas(LNG)is regarded as one of the cleanest fossil fuel and has experienced significant developments in recent years.The liquefaction process of natural gas is energy-intensive,while the regasificatio... Liquefied natural gas(LNG)is regarded as one of the cleanest fossil fuel and has experienced significant developments in recent years.The liquefaction process of natural gas is energy-intensive,while the regasification of LNG gives out a huge amount of waste energy since plenty of high grade cold energy(-160℃)from LNG is released to sea water directly in most cases,and also sometimes LNG is burned for regasification.On the other hand,liquid air energy storage(LAES)is an emerging energy storage technology for applications such as peak load shifting of power grids,which generates 30%-40%of compression heat(-200℃).Such heat could lead to energy waste if not recovered and used.The recovery of the compression heat is technically feasible but requires additional capital investment,which may not always be economically attractive.Therefore,we propose a power plant for recovering the waste cryogenic energy from LNG regasification and compression heat from the LAES.The challenge for such a power plant is the wide working temperature range between the low-temperature exergy source(-160℃)and heat source(-200℃).Nitrogen and argon are proposed as the working fluids to address the challenge.Thermodynamic analyses are carried out and the results show that the power plant could achieve a thermal efficiency of 27%and 19%and an exergy efficiency of 40%and 28%for nitrogen and argon,respectively.Here,with the nitrogen as working fluid undergoes a complete Brayton Cycle,while the argon based power plant goes through a combined Brayton and Rankine Cycle.Besides,the economic analysis shows that the payback period of this proposed system is only 2.2 years,utilizing the excess heat from a 5 MW/40 MWh LAES system.The findings suggest that the waste energy based power plant could be co-located with the LNG terminal and LAES plant,providing additional power output and reducing energy waste. 展开更多
关键词 waste energy recovery Power plant Liquid air energy storage Liquefied natural gas INTEGRATION
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Enhanced graph-based fault diagnostic system for nuclear power plants 被引量:1
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作者 Yong-Kuo Liu Xin Ai +4 位作者 Abiodun Ayodeji Mao-Pu Wu Min-Jun Peng Hong Xia Wei-Feng Yu 《Nuclear Science and Techniques》 SCIE CAS CSCD 2019年第12期8-21,共14页
Scheduled maintenance and condition-based online monitoring are among the focal points of recent research to enhance nuclear plant safety.One of the most effective ways to monitor plant conditions is by implementing a... Scheduled maintenance and condition-based online monitoring are among the focal points of recent research to enhance nuclear plant safety.One of the most effective ways to monitor plant conditions is by implementing a full-scope,plant-wide fault diagnostic system.However,most of the proposed diagnostic techniques are perceived as unreliable by operators because they lack an explanation module,their implementation is complex,and their decision/inference path is unclear.Graphical formalism has been considered for fault diagnosis because of its clear decision and inference modules,and its ability to display the complex causal relationships between plant variables and reveal the propagation path used for fault localization in complex systems.However,in a graphbased approach,decision-making is slow because of rule explosion.In this paper,we present an enhanced signed directed graph that utilizes qualitative trend evaluation and a granular computing algorithm to improve the decision speed and increase the resolution of the graphical method.We integrate the attribute reduction capability of granular computing with the causal/fault propagation reasoning capability of the signed directed graph and comprehensive rules in a decision table to diagnose faults in a nuclear power plant.Qualitative trend analysis is used to solve the problems of fault diagnostic threshold selection and signed directed graph node state determination.The similarity reasoning and detection ability of the granular computing algorithm ensure a compact decision table and improve the decision result.The performance of the proposed enhanced system was evaluated on selected faults of the Chinese Fuqing 2 nuclear reactor.The proposed method offers improved diagnostic speed and efficient data processing.In addition,the result shows a considerable reduction in false positives,indicating that the method provides a reliable diagnostic system to support further intervention by operators. 展开更多
关键词 nuclear power plants FAULT diagnosis SIGNED directed graph DECISION TABLE GRANULAR computing
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Development and Application of Maintenance Template in Pressurized Water Reactor Nuclear Power Plant 被引量:2
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作者 张圣 陈宇 +1 位作者 曹智鹏 莫春铌 《Journal of Donghua University(English Edition)》 EI CAS 2015年第1期162-165,共4页
Good practices of maintenance optimization in nuclear power field need to be effectively consolidated and inherited,and maintenance optimization can provide technology support to create a long-term reliable and econom... Good practices of maintenance optimization in nuclear power field need to be effectively consolidated and inherited,and maintenance optimization can provide technology support to create a long-term reliable and economic operation for nuclear power plants( NPPs) especially for a large number of nuclear powers under construction. Based on the development and application of maintenance template in developed countries,and combining with reliability-centered maintenance( RCM) analysis results and maintenance experience data over the past ten years in domestic NPPs, the development process of maintenance template was presented for Chinese pressurized water reactor( PWR) NPP,and the application of maintenance template to maintenance program development and maintenance optimization combined with cases were demonstrated. A shortcut was provided for improving the efficiency of maintenance optimization in domestic PWR NPP,and help to realize a safe,reliable,and economic operation for domestic NPPs. 展开更多
关键词 pressurized water reactor(PWR) nuclear power plant maintenance template maintenance program maintenance optimization
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Comparison of Risk Assessment for a Nuclear Power Plant Construction Project Based on Analytic Hierarchy Process and Fuzzy Analytic Hierarchy Process 被引量:6
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作者 Dae-Woong Shin Yoonseok Shin Gwang-Hee Kim 《Journal of Building Construction and Planning Research》 2016年第3期157-171,共15页
Recently, plant construction throughout the world, including nuclear power plant construction, has grown significantly. The scale of Korea’s nuclear power plant construction in particular, has increased gradually sin... Recently, plant construction throughout the world, including nuclear power plant construction, has grown significantly. The scale of Korea’s nuclear power plant construction in particular, has increased gradually since it won a contract for a nuclear power plant construction project in the United Arab Emirates in 2009. However, time and monetary resources have been lost in some nuclear power plant construction sites due to lack of risk management ability. The need to prevent losses at nuclear power plant construction sites has become more urgent because it demands professional skills and large-scale resources. Therefore, in this study, the Analytic Hierarchy Process (AHP) and Fuzzy Analytic Hierarchy Process (FAHP) were applied in order to make comparisons between decision-making methods, to assess the potential risks at nuclear power plant construction sites. To suggest the appropriate choice between two decision-making methods, a survey was carried out. From the results, the importance and the priority of 24 risk factors, classified by process, cost, safety, and quality, were analyzed. The FAHP was identified as a suitable method for risk assessment of nuclear power plant construction, compared with risk assessment using the AHP. These risk factors will be able to serve as baseline data for risk management in nuclear power plant construction projects. 展开更多
关键词 COMPONENT Analytic Hierarchy Process (AHP) Fuzzy Analytic Hierarchy Process (FAHP) nuclear Power plant Reactor Containment Building (RCB) Risk Assessment
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Self-propagating High-temperature Synthesis of Sm and Zr Co-doped Gd2Ti2O7 Pyrochlore Ceramics as Nuclear Waste Forms 被引量:1
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作者 谢达雁 张魁宝 +2 位作者 LI Weiwei LUO Baozhu GUO Haiyan 《Journal of Wuhan University of Technology(Materials Science)》 SCIE EI CAS 2021年第2期196-202,共7页
We reported a rapid synthesis of Sm^(3+)/Zr^(4+)co-doped Gd2Ti2O7 pyrochlore simulated nuclear wastes solidification by self-propagation plus quick pressing technique.With increment excess contents of Sm2O3 and ZrO2 f... We reported a rapid synthesis of Sm^(3+)/Zr^(4+)co-doped Gd2Ti2O7 pyrochlore simulated nuclear wastes solidification by self-propagation plus quick pressing technique.With increment excess contents of Sm2O3 and ZrO2 from 0 to 10wt%,the phase composition of the products is a mixed phase of pyrochlore structure and defective fluorite structure by X-ray diffraction(XRD)analysis and Raman spectrum.In addition,the SEM results demonstrate the fracture surface and microstructure of Gd2Ti2O7-based pyrochlore.The densified pyrochlore waste form exhibits high bulk density of 5.56 g·cm^(-3) and vickers hardness of 11.20±0.2 GPa.The leaching tests show that the elemental leaching rates of Gd,Sm,and Cu after 42 days are 1.92×10^(-4),1.51×10^(-4),and 3.90×10^(-3) g·m^(-2)·d^(-1),respectively. 展开更多
关键词 SHS PYROCHLORE immobilization of nuclear wastes EXCESS
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Biodegradation of Medicinal Plants Waste in an Anaerobic Digestion Reactor for Biogas Production 被引量:1
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作者 Kabir Fardad Bahman Najafi +3 位作者 Sina Faizollahzadeh Ardabili Amir Mosavi Shahaboddin Shamshirband Timon Rabczuk 《Computers, Materials & Continua》 SCIE EI 2018年第6期381-392,共12页
Glycyrrhiza glabra,Mint,Cuminum cyminum,Lavender and Arctium medicinal are considered as edible plants with therapeutic properties and as medicinal plants in Iran.After extraction process of medicinal plants,residual ... Glycyrrhiza glabra,Mint,Cuminum cyminum,Lavender and Arctium medicinal are considered as edible plants with therapeutic properties and as medicinal plants in Iran.After extraction process of medicinal plants,residual wastes are not suitable for animal feed and are considered as waste and as an environmental threat.At present there is no proper management of waste of these plants and they are burned or buried.The present study discusses the possibility of biogas production from Glycyrrhiza Glabra Waste(GGW),Mentha Waste(MW),Cuminum Cyminum Waste(CCW),Lavender Waste(LW)and Arctium Waste(AW).250 g of these plants with TS of 10%were digested in the batch type reactors at the temperature of 35℃.The highest biogas production rate were observed to be 13611 mL and 13471 mL for CCW and GGW(10%TS),respectively.While the maximum methane was related to GGW with a value of 9041 mL(10%TS).The highest specific biogas and methane production were related to CCW with value of 247.4 mL.(g.VS)-1 and 65.1 mL.(g.VS)-1,respectively.As an important result,it was obvious that in lignocellulose materials,it cannot be concluded that the materials with similar ratio of C/N has the similar digestion and biogas production ability. 展开更多
关键词 BIOGAS environmental threat lignocellulose substances medicinal plants residual wastes
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Development of SA-533 Type B CL. 1+SA-240 Type 304L roll-bonded clad steel plate for safety injection tank of CAP1400 nuclear power plant 被引量:2
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作者 HOU Hong ZHANG Hanqian +1 位作者 YUAN Xiangqian DING Jianhua 《Baosteel Technical Research》 CAS 2017年第1期18-25,共8页
Aiming to meet the demand of the country's nuclear demonstration project on the CAP1400 nuclear power plant,Baosteel uses the roll-bonding technology and develops the SA-533 Type B CL. 1+SA-240 Type 304L high-stre... Aiming to meet the demand of the country's nuclear demonstration project on the CAP1400 nuclear power plant,Baosteel uses the roll-bonding technology and develops the SA-533 Type B CL. 1+SA-240 Type 304L high-strength and high-toughness clad steel plate with a shear strength of over 310 MPa for the nuclear power plant's safety injection tank. The properties of the quenched and tempered and the simulated post-weld heat treatment states are systematically studied herein through a comprehensive inspection and evaluation of the composition,microstructure,and properties of the clad steel plate. The results show that the bonding interface has high shear strength and that the base metal has high strength and good toughness at low temperatures. Hence,the performance fully meets the technical requirements of the CAP1400 nuclear power plant's safety injection tank in the country's nuclear demonstration project. The roll-bonded clad steel plate can be used to manufacture the safety injection tank of the CAP1400 nuclear power plant. 展开更多
关键词 CAP1400 nuclear power plant safety injection tank SA-533 Type B CL. 1+SA-240 Type 304L rolling clad steel plate quenched and tempered simulated post-weld heat treatment property
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Active source seismic imaging on near-surface granite body:case study of siting a geological disposal repository for high-level radioactive nuclear waste 被引量:1
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作者 Wen Li Yi-Ke Liu +2 位作者 Yong Chen Bao-Jin Liu Shao-Ying Feng 《Petroleum Science》 SCIE CAS CSCD 2021年第3期742-757,共16页
In order to research whether it is suitable to set a geological disposal repository for high-level radioactive nuclear waste into one target granite body,two active source seismic profles were arranged near a small to... In order to research whether it is suitable to set a geological disposal repository for high-level radioactive nuclear waste into one target granite body,two active source seismic profles were arranged near a small town named Tamusu,Western China.The study area is with complex surface conditions,thus the seismic exploration encountered a variettraveltimey of technical difculties such as crossing obstacles,de-noising harmful scattered waves,and building complex near-surface velocity models.In order to address those problems,techniques including cross-obstacle seismic geometry design,angle-domain harmful scattered noise removal,and an acoustic wave equation-based inversion method jointly utilizing both the and waveform of frst arrival waves were adopted.The fnal seismic images clearly exhibit the target rock’s unconformable contact boundary and its top interface beneath the sedimentary and weathered layers.On this basis,it could be confrmed that the target rock is not thin or has been transported by geological process from somewhere else,but a native and massive rock.There are a few small size fractures whose space distribution could be revealed by seismic images within the rock.The fractures should be kept away.Based on current research,it could be considered that active source seismic exploration is demanded during the sitting process of the geological disposal repository for nuclear waste.The seismic acquisition and processing techniques proposed in the present paper would ofer a good reference value for similar researches in the future. 展开更多
关键词 Geological disposal repository nuclear waste Granite body Active source seismic exploration Near-surface velocity inversion
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Investigation on Flow Accelerated Corrosion Mitigation for Secondary Circuit Piping of the Third Qinshan Nuclear Power Plant 被引量:3
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作者 ZHAO Liang HU Jianqun +1 位作者 WU Zhigang WANG Kin 《Chinese Journal of Mechanical Engineering》 SCIE EI CAS CSCD 2011年第2期214-219,共6页
Flow accelerated corrosion(FAC) is the main failure cause of the secondary circuit carbon steel piping in nuclear power plants.The piping failures caused by FAC have resulted in numerous unplanned outages and tragic f... Flow accelerated corrosion(FAC) is the main failure cause of the secondary circuit carbon steel piping in nuclear power plants.The piping failures caused by FAC have resulted in numerous unplanned outages and tragic fatalities.The existing researches focus on the main factors contributing to FAC,which include metallurgical factors,environmental factors and hydrodynamic factors. Some effective FAC management methods and programs with long term monitoring and inspection data analysis are recommended.But a comprehensive FAC management system should be developed in order to mitigate and manage FAC systematically.In this paper,the FAC influencing factors are analyzed in combination with the operating conditions of the secondary circuit piping in the Third Qinshan Nuclear Power Plant(TQNPP),China(Third Qinshan Nuclear Power Company Limited,China).A comprehensive FAC mitigation and management system is developed for TQNPP secondary circuit piping.The system is composed of five processes,viz.materials substitution,water chemical optimization,long-term monitor strategy for the susceptible piping,integrity evaluation of the local thinning defects,and repair or replacement.With the implementation of the five processes,the material of FAC sensitive pipe fittings are modified from carbon steel to stainless steel,N_2H_4 and NH_3 are finally selected as the water chemical regulator of secondary circuit,the secondary circuit pips are classified according to FAC susceptibility in order to conduct long term monitoring strategy,and an integrity evaluation flow for local thinning caused by FAC in carbon steel piping is developed.If the component with local thinning defects is not fit-for-service,corresponding repair or replacement should be conducted.The comprehensive FAC mitigation and management system with five interrelated processes would be a cost-effective method of increasing personnel safety,plant safety and availability. 展开更多
关键词 秦山第三核电厂 客流调查 流程管理系统 水动力因素 设备安全性 二次回路 缓蚀 电路
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