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Multi-objective optimization and evaluation of supercritical CO2 Brayton cycle for nuclear power generation
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作者 Guo-Peng Yu Yong-Feng Cheng +1 位作者 Na Zhang Ping-Jian Ming 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2024年第2期183-209,共27页
The supercritical CO2 Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout,compact structure,and high cycle efficiency.Mathematical models of four Brayton c... The supercritical CO2 Brayton cycle is considered a promising energy conversion system for Generation IV reactors for its simple layout,compact structure,and high cycle efficiency.Mathematical models of four Brayton cycle layouts are developed in this study for different reactors to reduce the cost and increase the thermohydraulic performance of nuclear power generation to promote the commercialization of nuclear energy.Parametric analysis,multi-objective optimizations,and four decision-making methods are applied to obtain each Brayton scheme’s optimal thermohydraulic and economic indexes.Results show that for the same design thermal power scale of reactors,the higher the core’s exit temperature,the better the Brayton cycle’s thermo-economic performance.Among the four-cycle layouts,the recompression cycle(RC)has the best overall performance,followed by the simple recuperation cycle(SR)and the intercooling cycle(IC),and the worst is the reheating cycle(RH).However,RH has the lowest total cost of investment(C_(tot))of$1619.85 million,and IC has the lowest levelized cost of energy(LCOE)of 0.012$/(kWh).The nuclear Brayton cycle system’s overall performance has been improved due to optimization.The performance of the molten salt reactor combined with the intercooling cycle(MSR-IC)scheme has the greatest improvement,with the net output power(W_(net)),thermal efficiencyη_(t),and exergy efficiency(η_(e))improved by 8.58%,8.58%,and 11.21%,respectively.The performance of the lead-cooled fast reactor combined with the simple recuperation cycle scheme was optimized to increase C_(tot) by 27.78%.In comparison,the internal rate of return(IRR)increased by only 7.8%,which is not friendly to investors with limited funds.For the nuclear Brayton cycle,the molten salt reactor combined with the recompression cycle scheme should receive priority,and the gas-cooled fast reactor combined with the reheating cycle scheme should be considered carefully. 展开更多
关键词 Supercritical CO2 Brayton cycle nuclear power generation Thermo-economic analysis Multi-objective optimization Decision-making methods
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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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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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Fault prediction method for nuclear power machinery based on Bayesian PPCA recurrent neural network model 被引量:3
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作者 Jun Ling Gao-Jun Liu +2 位作者 Jia-Liang Li Xiao-Cheng Shen Dong-Dong You 《Nuclear Science and Techniques》 SCIE CAS CSCD 2020年第8期13-23,共11页
Early fault warning for nuclear power machinery is conducive to timely troubleshooting and reductions in safety risks and unnecessary costs. This paper presents a novel intelligent fault prediction method, integrated ... Early fault warning for nuclear power machinery is conducive to timely troubleshooting and reductions in safety risks and unnecessary costs. This paper presents a novel intelligent fault prediction method, integrated probabilistic principal component analysis(PPCA), multi-resolution wavelet analysis, Bayesian inference, and RNN model for nuclear power machinery that consider data uncertainty and chaotic time series. After denoising the source data, the Bayesian PPCA method is employed for dimensional reduction to obtain a refined data group. A recurrent neural network(RNN) prediction model is constructed, and a Bayesian statistical inference approach is developed to quantitatively assess the prediction reliability of the model. By modeling and analyzing the data collected on the steam turbine and components of a nuclear power plant, the results of the goodness of fit, mean square error distribution, and Bayesian confidence indicate that the proposed RNN model can implement early warning in the fault creep period. The accuracy and reliability of the proposed model are quantitatively verified. 展开更多
关键词 Fault prediction nuclear power machinery Steam turbine Recurrent neural network Probabilistic principal component analysis Bayesian confidence
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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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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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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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Future Expectation for China’s Nuclear Power 被引量:1
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作者 Huang Yuanjing 《Electricity》 2009年第1期10-16,共7页
China: the future of nuclear powerWang Yonggan: In terms of the highlighted issue ofenergy security, oil is of paramount importance, coal isthe foundation and electricity is the pivot according
关键词 HTGR s nuclear power Future Expectation for China
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Novel Technological Developments with Impacts on Perspectives for Mobile Nuclear Power Plants 被引量:1
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作者 Luciano Ondir Freire Delvonei Alves de Andrade 《World Journal of Nuclear Science and Technology》 2021年第4期141-158,共18页
New research developments suggest that nuclear reactors using fusion may enter the market sooner than imagined even for mobile applications, like merchant ship propulsion and remote power generation. This article aims... New research developments suggest that nuclear reactors using fusion may enter the market sooner than imagined even for mobile applications, like merchant ship propulsion and remote power generation. This article aims at pointing such developments and how they could affect nuclear fusion. The method is enumerating the main nuclear reactors concepts, identifying new technological or theoretical developments useful to nuclear field, and analysing how new recombination could affect feasibility of nuclear fusion. New technologies or experimental results do not always work the way people imagine, being better or worse for intended effects or even bringing completely unforeseen effects. Results point the following designs could be successful, in descending order of potential: aneutronic nuclear reactions using lattice confinement, aneutronic nuclear reactions using inertial along magnetic confinement, hybrid fission-lattice confinement fusion, and fission reactions. 展开更多
关键词 Fusion Reactors Mobile nuclear power Plants nuclear Reactors nuclear Merchant Ships Clean Energy
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A framework for nuclear power plant emergency response system
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作者 Wang-kun CHEN 《Nuclear Science and Techniques》 SCIE CAS CSCD 2010年第6期375-378,共4页
The purpose of this study is to establish an intelligent expert system for nuclear power plant emergency response.A new framework of environmental risk management methodology by the concept of pattern recognition was ... The purpose of this study is to establish an intelligent expert system for nuclear power plant emergency response.A new framework of environmental risk management methodology by the concept of pattern recognition was introduced in this paper.A knowledge-based decision support system for emergency response and risk management of nuclear power plant was also discussed.The mathematical pattern relationship of accidental release effects on neighboring area and the corresponding response measures were presented in this paper.With this decision system,the decision maker can specify the procedure and minimize their human error in the decision process.The improvement of risk response and the quality of management system could be upgraded by this system.Besides,the methodology can also be served as a basis for the future development of environmental risk response system design. 展开更多
关键词 Expert system Emergency response Risk management nuclear power plant
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Effects of Liaoning Hongyanhe Nuclear Power Plant on the Zooplankton Community in Summer of 2017
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作者 WANG Junjian TAO Zhencheng +3 位作者 WANG Yantao WEI Hao LIU Xin LI Chaolun 《Journal of Ocean University of China》 SCIE CAS CSCD 2020年第5期1140-1152,共13页
To evaluate the effects of the Hongyanhe Nuclear Power Plant on the zooplankton community in the surrounding seawater during summer, multiple environmental factors and zooplankton distribution along the east coast of ... To evaluate the effects of the Hongyanhe Nuclear Power Plant on the zooplankton community in the surrounding seawater during summer, multiple environmental factors and zooplankton distribution along the east coast of Liaodong Bay were investigated in the summer of 2017. In particular, the influences of seawater temperature, salinity, and chlorophyll a(Chl a) on the zooplankton community were analyzed. Zooplankton abundances and Chl a concentrations along the east coast of Liaodong Bay showed an initial increase followed by a decrease from July to September. During the three months, the zooplankton abundance was the highest(8116.70 ind m^(-3)) in August. The Shannon-Wiener index showed a downtrend from July to September, with the average value falling from 1.65 in July to 1.50 in September. Calanus sinicus, Paracalanus parvus, copepodid, and bivalve larvae were the dominant species/groups in the three months. The effects of the nuclear power plant's outlet on the environment factors were mainly reflected in the increased seawater temperature. Redundancy analysis showed that the zooplankton community was jointly affected by seawater temperature, salinity and Chl a concentration, and the degree of this impact varied monthly. The impact of seawater temperature on the zooplankton community was stronger than that of salinity. The primary impact of the Hongyanhe Nuclear Power Plant on the structure and distribution of the zooplankton community in the surrounding seawater during the summer was increased seawater temperature, which caused a reduction in the abundance of dominant species/groups. 展开更多
关键词 ZOOPLANKTON ABUNDANCE community structure DIVERSITY environmental factor Hongyanhe nuclear power Plant
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Size-dependent spatio-temporal dynamics of eukaryotic plankton community near nuclear power plant in Beibu Gulf,China
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作者 Lizhou LIN Haifeng GU +1 位作者 Zhaohe LUO Na WANG 《Journal of Oceanology and Limnology》 SCIE CAS CSCD 2021年第5期1910-1925,共16页
Pico-and nano-eukaryotic plankton are important members of marine ecosystems.To understand their community structure and spatio-temporal variations in the Beibu Gulf,and to study the impact of Changjiang Nuclear Power... Pico-and nano-eukaryotic plankton are important members of marine ecosystems.To understand their community structure and spatio-temporal variations in the Beibu Gulf,and to study the impact of Changjiang Nuclear Power Plant(CNPP)located in the northwest coast of the Hainan Island on the eukaryotic plankton,we studied these issues in the coastal water near CNPP bimonthly from February 2018 to January 2019 via 18 S Illumina sequencing.The results reveal a higher genetic alphadiversity and less beta-diversity of the plankton community in small-size(0.45-5μm and 5-20μm)fractions than in large-size(20-200μm and>20μm)fractions.The small-sized phytoplankton,including Micromonas(Chlorophyta)and Minutocellus(Bacillariophyta),as well as heterotrophic plankton,including Paraphysomonas(Chrysophyceae),Ellobiopsis(Dinoflagellates),and Syndiniales(Dinoflagellates),took up a considerable proportion in eukaryotic plankton community.In addition,it showed a slight temperature increase and no significant difference in eukaryotic plankton community between the outfall of CNPP and other sampling sites,suggesting that the impact of the thermal discharge from the CNPP on local eukaryotic plankton community was limited. 展开更多
关键词 nuclear power plant the Beibu Gulf eukaryotic plankton community high-throughput sequencing PICOPLANKTON NANOPLANKTON
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Investigation on the seismic response of nuclear power stations with a pile-raft foundation using centrifuge tests
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作者 Li Zhongcheng Yang Yang +3 位作者 Gong Weiming Yi Pik Cheng Dai Guoliang Liang Fayun 《Earthquake Engineering and Engineering Vibration》 SCIE EI CSCD 2022年第3期753-768,共16页
Research to reliably predict the seismic response of nuclear power stations with a pile-raft foundation is needed to meet the high safety requirements of nuclear power stations.In this study,a scaled superstructure wi... Research to reliably predict the seismic response of nuclear power stations with a pile-raft foundation is needed to meet the high safety requirements of nuclear power stations.In this study,a scaled superstructure with a 4×3 pile-raft foundation,which is constructed in Shanxi kaolin clay,is modelled.Accordingly,the characteristics of seismic response for nuclear power stations with a pile-raft foundation are analyzed using dynamic centrifuge tests.In particular,multiple earthquake motions with different magnitudes and frequency properties are utilized to map the relationship between structural response and properties of earthquake motions.The results show that the seismic response of the soil,raft,and structure are significantly affected by the natural frequency and magnitude of the earthquake motion.The soil surface acceleration is lower than the raft acceleration.The results provide a reliable reference to better understand the seismic response of nuclear power stations. 展开更多
关键词 dynamic centrifuge test seismic response pile-raft foundation nuclear power station soil-structure interaction
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Decomposition of oil cleaning agents from nuclear power plants by supercritical water oxidation
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作者 Shi-Bin Li Xiao-Bin Xia +2 位作者 Qiang Qin Shuai Wang Hong-Jun Ma 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第4期83-95,共13页
Oil cleaning agents generated from nuclear power plants(NPPs)are radioactive organic liquid wastes.To date,because there are no satisfactory industrial treatment measures,these wastes can only be stored for a long tim... Oil cleaning agents generated from nuclear power plants(NPPs)are radioactive organic liquid wastes.To date,because there are no satisfactory industrial treatment measures,these wastes can only be stored for a long time.In this work,the optimization for the supercritical water oxidation(SCWO)of the spent organic solvent was investigated.The main process parameters of DURSET(oil cleaning agent)SCWO,such as temperature,reaction time,and excess oxygen coefficient,were optimized using response surface methodology,and a quadratic polynomial model was obtained.The determination coefficient(R^(2))of the model is 0.9812,indicating that the model is reliable.The optimized process conditions were at 515 C,66 s,and an excess oxygen coefficient of 211%.Under these conditions,the chemical oxygen demand removal of organic matter could reach 99.5%.The temperature was found to be the main factor affecting the SCWO process.Ketones and benzene-based compounds may be the main intermediates in DURSET SCWO.This work provides basic data for the industrialization of the degradation of spent organic solvents from NPP using SCWO technology. 展开更多
关键词 Supercritical water oxidation Oil cleaning agent nuclear power plants Response surface methodology
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Reliability-Centered Maintenance-Based Maintenance Decision in New Nuclear Power Plants
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作者 黄立军 陈宇 +1 位作者 马沂荩 吴进 《Journal of Donghua University(English Edition)》 EI CAS 2016年第2期248-251,共4页
Taking the project of introducing reliability-centered maintenance( RCM) into maintenance decision in an AP1000 nuclear power plant( NPP) under construction as the research object,an improved RCM methodology was propo... Taking the project of introducing reliability-centered maintenance( RCM) into maintenance decision in an AP1000 nuclear power plant( NPP) under construction as the research object,an improved RCM methodology was proposed, and the application software and an RCM-based maintenance strategies management system were designed. In the pilot project,the RCMbased maintenance decision methodology had been applied to determining the maintenance strategies for two systems. Both the decision process and the results were described in this paper. The achievements of this project promoted the introduction and routinization of an advanced and effective maintenance decision mode in nuclear power field,which could provide valuable reference for new NPPs in China. 展开更多
关键词 reliability-centered maintenance(RCM) maintenance strategy maintenance decision maintenance program nuclear power plant(NPP)
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Operation of the main steam inlet and outlet interface pipe of a nuclear power station
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作者 黄桂平 Xuan Yabing +1 位作者 Zhang Linwei Liang Xuewei 《High Technology Letters》 EI CAS 2017年第4期434-437,共4页
A method is proposed to measure the process margin of the main steam inlet and outlet pipe of a nuclear power plant by using an industrial photogrammetry system. This method includes steps of preparation,image acquisi... A method is proposed to measure the process margin of the main steam inlet and outlet pipe of a nuclear power plant by using an industrial photogrammetry system. This method includes steps of preparation,image acquisition,image processing,and result analysis,as well as the final processing margin analysis,and so on. In particular,it suggests a specific method for target-point layout and design of shooting network for the main steam inlet and outlet pipe measurement,and then uses a method of sub-section photography and collation to measure the inner and outer surfaces of the nuclear power interface pipe. The machining tolerance analysis shows that the method can effectively test whether the machining tolerance data of the interface pipe's top surface,outer surface and the inner surface reach a critical value,which provides a reliable reference for the next step in this process,and it is a type of machining tolerance detection method worthy of popularisation. 展开更多
关键词 nuclear power interface pipe machining tolerance industrial photogrammetry system
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Property uniformity of thick nickel-based alloy plate for nuclear power steam-generator divider plate
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作者 AO Ying XU Changzheng HUANG Haiyan 《Baosteel Technical Research》 CAS 2021年第2期27-34,共8页
This paper introduces a thick 690 nickel-based alloy plate produced by the former Baosteel Special Steel Co.,Ltd.used as the steam-generator divider plate in the pressurized water reactor nuclear power plant.According... This paper introduces a thick 690 nickel-based alloy plate produced by the former Baosteel Special Steel Co.,Ltd.used as the steam-generator divider plate in the pressurized water reactor nuclear power plant.According to the product characteristics and design requirements of the thick nickel-based alloy plate,multidimensional sampling and testing were conducted to investigate its microstructure and mechanical properties.The results show that all the property indexes of the thick hot-rolled nickel-based alloy plate meet the design requirements,and there is good uniformity in the microstructure and mechanical properties in different dimensions.These findings indicate that China has mastered the core manufacturing technology of thick nickel-based alloy plates for their use as divider plates in nuclear power steam generators. 展开更多
关键词 nuclear power station nickel-based alloy divider plate thick hot-rolled plate
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Violation of the Convention on the Protection of the Black Sea against Pollution,Bucharest’s Convention of 1992 and the Sofia Protocol of 2018 by Turkish Government’s Sinop Nuclear Power Complex Project
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作者 Hayrettin Kilic Ismail Hakki Atal 《Journal of Environmental Science and Engineering(A)》 2021年第1期34-38,共5页
On September 12th,2020,the Turkish Ministry of Environment and Urban Planning issued a final approved version of an EIA(Environmental Impact Assessment)report for the Sinop(4,800 MWe)nuclear power plant and nuclear fu... On September 12th,2020,the Turkish Ministry of Environment and Urban Planning issued a final approved version of an EIA(Environmental Impact Assessment)report for the Sinop(4,800 MWe)nuclear power plant and nuclear fuel fabrication complex project,located on Turkey’s Southern Black Sea coastline,in the Sinop Providence,which will be built on a BOO(Build-Own-Operate)basis by an offshore company known as General Directorate of Electricity Generation Inc.(EUAS)International ICC,along with unknown shadowy partners and investors.This project violates the Convention on the Protection of the Black Sea against Pollution,namely,Bucharest’s Convention of 1992,and the Sofia Protocol of 2018 which are established to preserve the uniqueness of the Black Sea,sustain the fisheries,and protect marine life.The Black Sea is the largest anoxic water basin in the world with oxygen rich surface waters supporting marine life which constitute only about 13% of the Black Sea volume.For the rest of the entire Black Sea at a depth greater than 150-200 m,there is a permanent hydrogen sulphide zone devoid of life,the oxygen is completely absent after this level.This unique bio-hydrological characteristic has been regulating the preconditions of its following distinctive biodiversity for thousands of years.The biologically rich regions are only limited to only oxygen rich shelf zones,with depths of up to 50-100 m in the southern coast line,and in the northern Black Sea shallow-water areas with depths of up to 5-10 m.This water body,bordering the hydrogen sulphide zone,is approximately 200-300 m wide and averages 5-50 m deep,in which high concentrations of fish eggs and larvae strive,and circulate counterclockwise along 4340 km coastline of the Black Sea. 展开更多
关键词 Bucharest convention PROTECTION Black Sea nuclear power plant POLLUTION
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Nuclear Power——China's Important Energy Pillar
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作者 Yu Ming 《China's Foreign Trade》 1996年第4期28-28,共1页
Nuclear power will be a must for Chinafor its energy development to meet thelarge energy demand of its hugepopulation and rapid economic development. China’s self-designed Qinshan NuclearPower Station of 300,000 kw i... Nuclear power will be a must for Chinafor its energy development to meet thelarge energy demand of its hugepopulation and rapid economic development. China’s self-designed Qinshan NuclearPower Station of 300,000 kw is now runningsmoothly.Its power generation units’ loadfactor was 66 percent in 1993 and 68 percentin 1994.Through examination andmeasurement,it can be certain that the designand manufacture quality of China-made fuelauxiliaries,steam generators and turbo-generation units at the station are reliableand satisfactory,with its radiative materialdischarge to the environment far below thenational level,not affecting the ambientenvironment radiative level.In July,1995,the Qinshan Nuclear Power Station wasaccepted by the State,enabling China 展开更多
关键词 WILL nuclear power China’s Important Energy Pillar
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Unit 1 of Ling’ao Nuclear Power Plant phase II underwent hot functional test successfully
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作者 Liu Chunsheng 《Electricity》 2010年第2期8-,共1页
On February 25, the Unit 1 of Ling’ao Nuclear Power Plant phase II underwent a 41-day-long hot functional test successfully with its major systems satisfying the requirements for
关键词 II TEST ao nuclear power Plant phase II underwent hot functional test successfully Unit 1 of Ling
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