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2016 Vol. 3, No. 3

Feature Articles
New Challenges of "Going Out" Strategy for Nuclear Power in China
Weihong ZHOU
2016, 3(3): 1-5. doi: 10.16516/j.gedi.issn2095-8676.2016.03.001
Abstract:
China's third generation nuclear power technology is facing new challenges with such problems as the overtime construction and higher cost due to the immaturation of proto type reactors. The article presents a concise analysis on the feedback from Finland, France, Russia as well as China. In the context of China's New Normal economy and the on-going reform of electric power market, it makes some suggestions in regard of the competitiveness of investment and overseas projects.
Feature Article
The Role of Nuclear Power in China's Medium and Long Term Energy Supply System
Xiaobing SUN
2016, 3(3): 6-15. doi: 10.16516/j.gedi.issn2095-8676.2016.03.002
Abstract:
Studying the development of nuclear power needs to be placed in the macro energy system to take comprehensive consideration. In this paper, the supply and demand situation of China power supply is studied. And the power supply and demand balance model is established. Considering eleven kinds of boundary conditions and the reference basis of major developed economies energy development history, this paper establishes six energy consumption prediction models of primary energy consumption before 2040, and gives "nuclear low value" and "nuclear high value" two kinds of prediction results. This paper analyzes the history of the development of nuclear power in the world. According to the development characteristic of five stages, the paper discusses the driving force, influencing factors and other issues of deferent development stages of nuclear power. In the meanwhile, this paper also studies nuclear development history in three typical countries. In this paper, the world uranium resources and storage ratio are studied. At the same time, the conversion ratio of uranium resources is defined to measure the transformation efficiency of uranium resources. The main conclusions are as follows: (1) Chinese fossil energy consumption will peak in 2030, and primary energy consumption will enter or maintain the slow growth stage; (2) In the long term, nuclear energy and non-water renewable energy will share the new energy consumption and the substitution of fossil energy needs; (3) In power surplus situation, large-scale construction of nuclear power is expected to be postponed until 2025; (4) To 2040, total energy consumption Chinese is expected to reach 5.74×109 tce, and the nuclear energy consumption accounts for between 4.5% to 7.5%, and non-water renewable energy consumption accounts for more than 13.6% to 16.6%; (5) In overall, the world has plenty of uranium resources to meet the "uranium based" nuclear long-term development. In addition, the price of uranium resources before 2040 will not be returned to the high level in 2007; (6) Transformation of uranium resources in China is only 56.6% of the world average. And there is the need to improve the technical level and processing capacity in the spent fuel treatment and fuel cycle utilization.
Radiation and Shielding Design of Hengjian Proton Medical Facility
Qingbiao WU, Yi PENG, Qingbin WANG, Bin ZHOU
2016, 3(3): 16-22. doi: 10.16516/j.gedi.issn2095-8676.2016.03.003
Abstract:
Hengjian Proton Medical Facility (HJPMF) is the first proton therapy device being built in Guangdong province. To ensure the radiation safety of HJPMF, two methods of emprical formulas calculation and Monte Carlo codes simulation were used to calculate and analyze its prompt radiation and induced radioactivity, and optimization design for its original shielding structure was conducted according to dose limit. The results shown that, the original shielding structure basically satisfies the requirement of shielding prompt radiation, but the thickness of outer concrete wall can be optimized and decreased greatly by soil shielding to save cost, and the thickness of several mazes and shielding walls can be optimized. The results also shown that, the induced dose rates from components in cyclotron room and from patients in treatment room are comparatively large and should be governed strictly. The research proved that both the empirical formulas and FLUKA or MCNPX code can be used to shielding design for proton medical facility, but the Monte Carlo codes are more suitable to the situations with sophisticated structure and induced radioactivity.
Nuclear Power Technology
Fuel Management Study and Economic Analysis of Long-term Refueling for Qinshan-II NPP
Hong YAO, Guoming LIU
2016, 3(3): 23-26,15. doi: 10.16516/j.gedi.issn2095-8676.2016.03.004
Abstract:
The fuel management study on long-term refueling is presented for Qinshan-II NPP. The four units of Qinshan-II NPP adopt OUT-IN reloading pattern and annually refueling now, with 36 assemblies containing 3.7% enriched UO2 fuel. For 18-month long term refueling, 44 assemblies with 4.45% enriched fuel and IN-OUT reloading pattern will be used. However, the cycle length of designed long-term reloading pattern is not enough, as a result, the NPP utilization is reduced. A fuel management strategy, employing 48 assemblies with 4.45% enriched fuel and IN-OUT reloading pattern, is introduced. The economic analyses of the three fuel management strategies, including the income of electricity generation, expenditure of fuel assembly cost and effect of NPP Outage frequency, are investigated. Several advantages are deduced by compare analysis. So the introduced strategy is recommended for the Qinshan-II NPP 18-month long term refueling.
Research on Transmission Planning of Large-scale Nuclear Power Plant
Jing GENG
2016, 3(3): 27-30. doi: 10.16516/j.gedi.issn2095-8676.2016.03.005
Abstract:
Nuclear power developing had been an important measure for our country to response the climate change and energy structure adjustment .In this project we studied and analyzed transmission planning of the 6 × 1250MW L nuclear power plant connected to GuangDong Province. Based on the determining of transmission direction and existing channel transmission capacity, we proposed two categories of four kinds of transmission program, we used PSD to calculated and simulated those program in power flow distribution, stability checking, short-circuit current level , economic and other aspects, after comprehensive comparison drawn we got the recommended program . The results shown that the recommended program (each three 500kV lines connect to A substation and B substation ) is technical and economic optimal solution, and meet the full electricity transmission. We recommend this program for other similar large-capacity nuclear power plants transmission planning.
Comprehensive Evaluation the Nuclear Power Energy Saving and Emission Reduction of Guangdong Province Based on the Entropy Method
Xiaomin LIU, Zhihui LIU, Zhe SHI
2016, 3(3): 31-35. doi: 10.16516/j.gedi.issn2095-8676.2016.03.006
Abstract:
Guangdong province is taken to analyze the comprehensive effect of energy saving and emission reduction since the development of nuclear power. According to the statistic data by Guangdong province from 1993 to 2010, Entropy method should be applied to make a comprehensive evaluation on energy saving and emission reduction effect in terms of four aspects, namely, energy consumption, pollutants emission, pollution control, and economic benefit. The result shows the comprehensive effect of energy saving and emission reduction presents the tendency of increasing in Guangdong province during 1993-2010. Meanwhile, total consumption of coal and petrol per unit of GDP, the total production of thermal power and total emission of CO2, and comprehensive energy consumption present a tendency of decreasing. The total production of nuclear power and hydropower per unit of GDP varies within a small range, but nuclear power and hydropower account for a small percentage in the power supply.
Hydrogen Removal Analysis in Severe Accident Induced by Loss of Feed Water for XUDAPU Nuclear Power Plant
Yang LIU, Xueyao SHI
2016, 3(3): 36-39. doi: 10.16516/j.gedi.issn2095-8676.2016.03.007
Abstract:
After loss of feed water accident, if the safety features fail to start up, the primary will loss heat sink, which may lead core uncover to generate hydrogen by Zirconium-Water Reaction. The hydrogen release to the containment could cause deflagration or detonation, which would produce both high thermal and pressure loads on the containment. This paper use MAAP4 to analyze the hydrogen removal capability after the severe accident induced by loss of feed water.
Analysis on Power Control System of Nuclear Power Plant
Qiang MENG, Danhua WANG
2016, 3(3): 40-44,35. doi: 10.16516/j.gedi.issn2095-8676.2016.03.008
Abstract:
In order to study the power control mode of each reactor type, based on the HTR-PM, VVER-1000 PWR, CPR1000 PWR, AP1000 analysis and comparison, the reactor power control system research shows that the control mode of reactor power control system HTR-PM which is the most simple, has great advantages, but HTR-PM reactor power control system has not been really practical operation, the realization of its control concept still need to continuously optimize and improve.
Design Improvement of Steam Generator Blowdown System
Shichao HAN, Jiaming ZHAO, Cuiyun WANG, Bin ZHAO
2016, 3(3): 45-47,53. doi: 10.16516/j.gedi.issn2095-8676.2016.03.009
Abstract:
According to the results of the full range of accident analysis, in case of steam generator tube rupture, in order to make affected SG water level will not rise too fast, and need to control the affected SG water level and pressure by steam generator blowdown system. According to design improvement of steam generator blowdown system, increase the system design bases, the blowdowns are routed to the IRWST inside the containment, in order to depressurize affected SG pressure and control affected SG level, to prevent the affected steam generator is filled with water, meet the requirements of steam generator blowdown system in the design basis accident under the safety function. The improvement design can satisfy the third generation nuclear power technology, provide theoretical basis for the safety of the third generation nuclear power in China.
Allocation and Optimization of the Cooling Tower About 1 000 MW NPP
Hui HE
2016, 3(3): 48-53. doi: 10.16516/j.gedi.issn2095-8676.2016.03.010
Abstract:
Based on the 1000MW nuclear power station cooling tower's allocation and optimization, the high-level water collecting cooling tower's annual operating costs is less than the conventional tower's, it's used by collection device, and can effectively reduce the pump geometry head, and also can save the annual operating costs. The larger of the filling area, it can get the more economic advantages of using high-level collection device. The numerical simulation according to the conclusions, the high-level water collecting cooling tower should be used by depth optimization about filling arrangement, reducing the thickness of the external filling, increasing the thickness of the internal filling, and ultimately finishing the overall thermal performance of the cooling tower.
Research on Maintenance Locking Device of Main Steam Valve of NPP
Chen XI, Hongwei HU, Hongwei DENG
2016, 3(3): 54-56. doi: 10.16516/j.gedi.issn2095-8676.2016.03.011
Abstract:
This paper introduces the maintenance locking device of main steam valve in the nuclear power plant. This application is used to avoid main steam valve displacement during maintenance in nuclear power generators. The locking device by adjusting the distance of the screw rod and the main steam valve, the main steam valve positioning and locked, lock tight main steam valve function in maintenance, so as to meet the steam turbine manufacturers on the installation and maintenance turbine interface without stress. At the same time, through the specification of the design, simplify the construction site operation difficulty, achieve the standard, high accuracy of maintenance requirements.
Fine Design for Turbine Room Ventilation System of NPP
Wenlong SUN
2016, 3(3): 57-62. doi: 10.16516/j.gedi.issn2095-8676.2016.03.012
Abstract:
Conventional ventilation calculation methods and design scheme of nuclear power plant turbine room can not determine the distribution of temperature and velocity in turbine room. The distribution of temperature and velocity could be visually seen by the use of Computational Fluid Dynamics (CFD) software to simulate, analysis and evaluate turbine room indoor thermal environment . What's more, design scheme could be easily adjusted and analyzed to meet the temperature design requirements by CFD method. Fine predictions of CFD could provide practical design strategies and scheme correction means for the ventilation design of hot workshop. Design using CFD method could tap the highlights of the ventilation system, providing a reliable design tools.
Suggestions on Fire Fighting Design for Conventional Island in Nuclear Power Plants
Mingcai WANG, Weibing MAO, Minfa ZHENG
2016, 3(3): 63-65,62. doi: 10.16516/j.gedi.issn2095-8676.2016.03.013
Abstract:
Some suggestions have been provided on fire fighting design of conventional island in nuclear power plants from the point of view of safe operation and equipment maintenance. Vrious fire fighting sstems in conventional island in nuclear power plants had been sorted out basing on fire fighting system design specification and operational feedback. Setting recommendations on the traps and exhaust valves as well as design principle of exciter fire fighting system have been proposed. Flow indicator and closed nozzle arrangement precautions and fire fighting system valve arrangement recommendations in conventional island in nuclear power plants have also been provided. This work provides some guidance for Fire fighting designers of nuclear power plants.
Research on the Assessment Method of Doses to Infants from Ingestion
Pinghui ZHENG, Xiaoliang WANG, Zhanghui XIONG, Wei ZHENG
2016, 3(3): 66-69,90. doi: 10.16516/j.gedi.issn2095-8676.2016.03.014
Abstract:
Public individuals are devided into four age groups of adult, youth, child and infant due to the difference in food consumption, living habit and age-dependent dose coefficients in the assessment of doses to public individuals from effluents of nuclear power plant under operational states. There are great uncertainties and difficuties in the investigation of characteristic and amount of infant food. Two assessment methods are applied to calculate the internal exposure dose to infants from ingestion: one is calculated from the investigated food cunsumption data, the other is calculated by dose coefficients for infants consuming breast-milk after intake by the mother. It can be concluded from the calculation results that doses to infants from ingestion calculated in two methods are close, but doses from different radionuclides vary significantly. Proper assessment mothod should be chosen in application according to the investigated food cunsumption data and infant age.
Study on Cold Insulation Design of Closed Air Curtain Door in Cold Region: A Case of Nuclear Power Turbine Generator House of Conventional Island in Liaoning Hongyanhe NPP
Lei JIN, Zhenyu LUO, Bo ZHOU
2016, 3(3): 70-72. doi: 10.16516/j.gedi.issn2095-8676.2016.03.015
Abstract:
In order to satisfied the equipment normally operate and the nuclear power plant safe in cold area, this paper discusses the conventional island of nuclear power steam turbine generator room a closed air curtain cold insulation characteristics of the gate structural approach, making the Liaoning Hongyanhe Nuclear power plant as example. Through the use of this gate to reduce energy loss, to meet the nuclear power plant steam turbine plant boundary temperature is greater than or equal to 5 ℃ requirements, saving the standard coal 85 kg per day.
In-situ Rockmass Test and Numerical Simulation of Basalt Waste Isolation Project in Handford
Wentang ZHENG, Cong SHI
2016, 3(3): 73-78,95. doi: 10.16516/j.gedi.issn2095-8676.2016.03.016
Abstract:
As the hard bedrock sites decreases gradually, the nuclear safety related structures of NPP has been demonstrating the foundation suitability of the weathered rock, half-diagenesis rock, sedimentary rock and the shallow buried basaltic bedrock under the wide quaternary overburden layer of costal plain, but there are few recent research on basaltic foundation suitability which columnar joints well developed. In this investigation we analyzed the in-situ colmunar basaltic rockmass test and numerical simulation results of Basalt Waste Isolation Project(BWIP) in Hardford, then used the three-dimensional discrete element software 3DEC and Voronoi diagrams to calculate the deformation modulus of irregular colmunar basaltic rockmass. The results shown that the numerical simulation coincide better with the in-situ rockmass test which the numerical solution of the deformation modulus parallel to the axial direction of BWIP is 20.19 GPa while the in-situ rockmass test result is 20 GPa. This work provide some guidance for further numerical simulation on foundation suitability of colmunar basaltic rockmass which can be applicated into the sitting of NPP and disposal repository.
Study on the Seismic Reliability of Steel Containment
Xiaomeng LI
2016, 3(3): 79-84. doi: 10.16516/j.gedi.issn2095-8676.2016.03.017
Abstract:
In recent years, more and more high-power nuclear power plants were constructed in China to meet the increasing needs of electricity. The volume of the containments in nuclear power plants increases with the increase of the power level. Therefore, accessing the ability of steel containment to resist strong earthquakes has attracted more attention recently. So far, the most seismic analysis methods are based on deterministic methods. In fact, the parameters in the engineering projects, such as geometry, material and load value, are usually uncertain. The seismic loads aslo have a complex statistical change, which is one of the natural properties of seismic wave. Therefore, the traditional deterministic methods are difficult to verify the safety of the structure. In this article, the seismic reliability of the large steel containment was studied. The random seismic response spectrum under different probabilities was established according to the stationary stochastic model. The parameters of the stationary stochastic model were obtained from Chinese seismic code. Two methods of seismic reliability analysis were considered. One is under deterministic seismic intensity, the other is under the certainty probabilities. Finally, the sensitivity parameters were calculated based on the Monte Carlo method. This article will provide some references for the seismic reliability design of the steel containment.
Reliability Application and Research of Domestic DCS System in Ultra-supercritical Unit
Fei LI
2016, 3(3): 85-90. doi: 10.16516/j.gedi.issn2095-8676.2016.03.018
Abstract:
Automatic control system is the nerve center, operation center and safety barrier of major technical equipment, known as the " brain" of major technical equipment. No independent of automatic control system, no independent of major technical equipment manufacture. The reliability of DCS system has been of concern to users.Therefore, Domestic DCS in ultra-supercritical units successful application, make an important contribution to the development of China's thermal power automation control industry technology, and accumulate valuable experience for application and technical promotion of Domestic DCS in the ultra-supercritical generating units' projects, and play a promoting role in the application of the entire domestic DCS technology.
Geotechnical Engineering Analysis of a Nuclear Power Plant with Heterogeneous Foundation
Yong LI, Runming ZHANG, Wentang ZHENG
2016, 3(3): 91-95. doi: 10.16516/j.gedi.issn2095-8676.2016.03.019
Abstract:
With the increasing power demand in China, the nuclear power development in non hard rock foundation, non igneous rock foundation and non homogeneous foundation will be incorporated into the future in the design of nuclear power plant site types. Therefore, non homogeneous soil nuclear power plant foundation geotechnical engineering investigation and analysis in the area of professional and technical personnel of a primary problem. This paper in a sedimentary rock nuclear power plant as an example, according to the characteristics of the site, through the rock classification, weathering degree division, and then each of the nuclear island foundation engineering geological unit division, put forward corresponding geotechnical design parameters proposed non-homogeneous foundation geotechnical engineering analysis method for the non homogeneous ground nuclear power development to provide technical support and on non homogeneous ground nuclear power plant of geotechnical engineering investigation has certain guiding significance.
Study on Hydrogeological Investigation of Nuclear Power Station
Xueling HU, Min ZHANG, Haiyi MA
2016, 3(3): 96-99. doi: 10.16516/j.gedi.issn2095-8676.2016.03.020
Abstract:
Nuclear power as a clean and environmentally friendly energy, in the economic and social development of the important role is becoming increasingly prominent. China as a developing country with rapid economic and social development attaches great importance to the status of nuclear power in the national economic development strategy. From 1970s nuclear power research and development, China's nuclear power has achieved rapid development. With the development of nuclear power, the study on the nuclear power in many aspects of the rapid development. In this paper, the research of nuclear power plant in the aspects of hydrogeological investigation is discussed, in order to provide a reference for the future research of nuclear power station project.
Nuclear Power Construction
Application of Plastic Drainage Plate Combined with Surcharge Preloading: A Case Study of Water Intake Channel in a Nuclear Power Plant
Nanbai TAN, Qian WANG
2016, 3(3): 100-103,111. doi: 10.16516/j.gedi.issn2095-8676.2016.03.021
Abstract:
According to the development of coastal nuclear plants in the 21st century, the coastal foundation treatment has been the main problem to the coastal nuclear plant construction. A coastal nuclear plant built a water intake channel on Dajin island. To ensure the rationality of technology and economy, and solve the stability problems of the coastal soft foundation, the project finally used the plastic drainage plate combined with surcharge preloading technology. After the construction period and a long time observation, the settlement is basically stable, the foundation treatment technology in the application of this project has been proved successful. And provides a valuable experience to the coastal foundation treatment.
Application of Deep Mixing Technique on Reinforcement of Nuclear Safety Foundation
Rongsheng YANG, Qian WANG
2016, 3(3): 104-107. doi: 10.16516/j.gedi.issn2095-8676.2016.03.022
Abstract:
This article introduces the application of deep cement mixing method in loose foundation (sand and gravel backfill) treatment and the changing of wave velocity, loading capacity, modulus of deformation and other performance index before and after using this method. The deep cement mixing method is seldom used in loose foundation (sand and gravel backfill) treatment. Its application is even rarer in treating the backfilled foundation with nuclear safety requirement. Therefore, this technique is innovative and serves as a good example for the future foundation consolidation and treatment.
Application of High-pressure Grouting Foundation Treatment Based on Increasing Shear Velocity in Taishan Nuclear Power Plant
Qian WANG, Zongbin LOU, Ming WU
2016, 3(3): 108-111. doi: 10.16516/j.gedi.issn2095-8676.2016.03.023
Abstract:
To meet nuclear safety criteria and have an anti-seismic function, buildings in a nuclear power plant should locate on bed rocks or rocks with a shear wave velocity greater than 400m/s. Foundation treatment is needed if the rock does not meet the above condition. Through an introduction on the foundation treatment of the liquid waste hold up tanks building in Taishan Nuclear Power Plant, comparison and analysis on the advantages and disadvantages of two methods are made in this article, namely excavation and backfill by plain concrete method and jet-grouting method. Practice has proven that under certain condition, jet-grouting method could efficiently increase the shear wave velocity. By adopting this method, slope excavation and retaining can be avoided, thus with a smaller constructive safety risk and a relatively lower cost. This method is fully fit for foundation with thick backfilled soil layer.
Soil Layer Seismic Response Analysis for a Nuclear Power Plant Backfill Site
Jiangfeng FANG, Long DU
2016, 3(3): 112-115,126. doi: 10.16516/j.gedi.issn2095-8676.2016.03.024
Abstract:
In this paper, used the engineering analogy method, obtain the dynamic parameters of rockfill materials. Calculated the seismic response of backfill site by SHAKE91 calculating program. The calculation results show that the response spectrum acceleration amplitude of backfill site surface increases significantly than the bedrock surface. And this paper can be a reference for seismic response analysis of general backfill site.
Research on Concrete Management Patterns of HPR1000 NPP
Zhengyu HUANG
2016, 3(3): 116-121. doi: 10.16516/j.gedi.issn2095-8676.2016.03.025
Abstract:
This paper introduces the current situation of concrete management pattern in domestic nuclear power project and analyzes the advantages and disadvantages of concrete supply management patterns bewteen plan A and plan B for HPR1000 nuclear power project. Considering the great demand of concrete for HPR1000 nuclear power project, the paper mainly makes contrastive study to the A and B Supply pattern from the economic aspect. By making comprehensive analysis, it is concluded that A Supply is the optimal pattern from the perspective of reducing cost and project management. It is hoped that the research can provide reference for concrete management pattern of the following nuclear power project with the same type of unit.
Research on Construction of the Owner Project Quality Supervision and Management Mechanism Under the NPP General Contract Mode
Xin LUO
2016, 3(3): 122-126. doi: 10.16516/j.gedi.issn2095-8676.2016.03.026
Abstract:
As the project management level of our country continues to improve, the engineering contracting mode in engineering application is gradually deepening. Especially in the petroleum, chemical and other industries use earlier, but for nuclear power engineering general contracting mode in China started late, especially in nuclear power engineering because of " nuclear" and other projects has a special side, that is, the need to more high quality to ensure nuclear safety. As the owners of nuclear power party how to do the general contracting mode of engineering quality supervision management ponder. This article from 5 aspects elaborated how to build the nuclear power project general contracting mode of the owner of the project quality supervision and management mechanism, in order to achieve from the mechanism to ensure the quality of nuclear power projects.
Problems and Countermeasures of Nuclear Publicity
Huan GAO
2016, 3(3): 127-130,141. doi: 10.16516/j.gedi.issn2095-8676.2016.03.027
Abstract:
The nuclear publicity problems of civil nuclear power companies are analyzed, including the system and mechanism of the nuclear publicity is imperfect, and the publicity method is outdated, the publicity resource is lack and some specified issues during the nuclear development are not solved. For these problems mentioned above, the countermeasures of nuclear publicity are proposed here. It includes the system and mechanism construction, capability building, popular science propaganda, information disclosure, public participation and public sentiment reply. Through these countermeasures, the nuclear publicity is hopeful to be improved, for the purpose of sharing experience of the nuclear publicity and promoting nuclear power projects construction. And it also could be support the sustainable development of the nuclear power.
Meeting Information
An Overview of 11th Annual China Nuclear Power Congress
Editorial Board of Southern Energy Construction
2016, 3(3): 131-137. doi: 10.16516/j.gedi.issn2095-8676.2016.03.028
Abstract:
To develop China nuclear industry more efficiently, and to draw attention to accelerate China 'Go Global’ Strategy, the 11th Annual China Nuclear Power Congress which is hosted by Shanghai Municipal Nuclear Power office and China Energy Engineering Corporation Guandong Electric Power Design Institute(GEDI), and co-organized by China Nuclear Energy Association and Nuclear Industry Exploration & Design, and organized by Noppen Group has been held in GEDI on August 26th, 2016. This forum strategically discusses the practice and prospect of nuclear development in China, emphasizes the importance of nuclear safety supervision, explores the intensively collaborative and technological innovation to make a new nuclear breakthrough, introduces the latest technological characteristics and project progress of on-built reactor types in China which are HPR1000(Hua-long Pressurized Reactor), China fast reactor technology, high temperature gas cooled reactor of national science and technology major project and so on. Moreover, intelligent manufacturing of nuclear equipment, improving economical efficiency of NPPs through technology innovation are discussed in detail. This forum has important significance to develop the China nuclear technology.
Communications for All Things: An Idea Whose Time has Come
Yang CAO
2016, 3(3): 138-141. doi: 10.16516/j.gedi.issn2095-8676.2016.03.029
Abstract:
As an annual flagship academic conference for global information and communication industry, IEEE internation conference on communications (IEEE ICC) presents the cutting-edge research and the latest trend of communication technologies. In this paper, we will introduce the latest advances in 5G, IoT and smart grid communications at IEEE ICC 2016.