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About Journal

Quarterly Publication,Start in 2014.12
Supervisor:China Southern Power Grid Digital Media Technology Co., Ltd.
China Energy Construction Group
Guangdong Electric Power Design and Research Institute Co., Ltd.
Editor:Editorial Board of S. ENERGY CONSTR.
Publisher:Energy Observer Magazine Co., Ltd.
Honorary Chairman:WU Yun
Chairman:HUANG Zhiqiu
Journal President:WANG Yongji
Editor-in-chief:FAN Yongchun 
Associate Editor:ZHANG Chunwen, CHENG Xiaojiu
Editorial Director:ZHENG Wentang
Address:1 Tianfeng Road, Science City, Huangpu District, Guangzhou, P. R. China
Tel:+86-20-32116683; 32115630
ISSN 2095-8676
CN 44-1715/TK
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Technical and Economic Study on Heating Transformation Scheme of Coal-fired Units
Weixuan XU
 doi: 10.16516/j.gedi.issn2095-8676.2022.03.010
[Abstract](15) [FullText HTML](4) [PDF 14564KB](1)
  Introduction  In order to solve the prominent contradiction between electric load and heat load faced by coal-fired units and ensure the heat source supply of units in winter, it is necessary to study the heating transformation scheme to break its thermoelectric coupling relationship.   Method  This paper made a model analysis of two heating transformation modes of a type of 300 MW coal-fired unit, compared the heating capacity and other data before and after the unit transformation, and studied the thermoelectric decoupling heating transformation scheme in line with the production conditions. And the economic effect of heating transformation of cogeneration units was summarized.   Conclusion  Through the analysis of the heating model in this paper, it can be seen that the coal-fired unit only relies on steam extraction for heating, which is greatly restricted by the power load. The heating capacity at high power load is 2~3 times that at low power load. When the electric load is severely limited, its heating capacity cannot meet the heating demand in winter. But after retrofit of high back pressure and modification of the cylinder, the capacity of peak shaving increases, and the heating capacity increases to 3~4 times under the same electric load, which effectively solved the problem.  Result  The research result can be used as a reference for the heating transformation of the same type of coal-fired units in the future.
Review on the Research Progress of Primary Frequency Modulation Technology for Thermal Power Units
Chunfeng YUAN, Kaihui LIU, Fan ZHANG, Hao Yang, Chenyang SUN, Shuzhou WEI, Jinxing WANG
Accepted Manuscript  doi: 10.16516/j.gedi.issn2095-8676.2022.03.001
[Abstract](176) [FullText HTML](70) [PDF 1421KB](33)
  Introduction  The primary frequency modulation technology of thermal power unit has been considered as an important content to ensure the safe and stable operation of power grid.   Method  In this paper we reviewed the current primary frequency modulation technology, the auxiliary primary frequency modulation technology, the coupled frequency modulation control strategy and the potential development direction of primary frequency modulation technology.   Result  The results show that the primary frequency modulation technology for the unit mainly includes regulating valve pre-throttling, adjustable regenerative steam extraction frequency modulation and condensate water throttling frequency modulation. Among them, the condensate water throttling frequency modulation technology should be the main mode. Auxiliary primary frequency modulation technology is mainly based on the fast-response rate characteristics of flywheel energy-storage and battery to meet the unit input and output requirements. The focus and difficulty of coupled auxiliary frequency modulation technology are then analyzed. The system modeling and control strategy research based on frequency modulation technology can optimize the matching between unit parameters.   Conclusion  Thus, we compared the application status of primary frequency modulation technology in recent years, and it is considered that flywheel energy storage primary frequency modulation and sliding pressure operation optimization will be the key development direction.
Controlled Nuclear Fusion Power Engineering Technology
The Progress of Error Field Investigation in Magnetically Confined Fusion Tokamak Reactor
Huihui WANG
2022, 9(2): 1-18   doi: 10.16516/j.gedi.issn2095-8676.2022.02.001
[Abstract](55) [FullText HTML](15) [PDF 2776KB](6)
  Introduction  Tokamak is recognized as the most feasible program for fusion power source, however various physical and engineering technology problems should be overcome before being power source. Error field, as inevitable non-axisymmetric perturbation magnetic field, can induce locked mode and degrade plasma stored energy, and further degrade the fusion reaction rate, or even resulting in disruption and damaging first wall of the device, threatening the safety and economy of fusion reactors. Therefore, it has been considered to be one of the most concerned problems in tokamaks over 30 years.   Method  To clarify the progress of error field investigation, we reviewed the history of error field investigation, summarized the research achievements over 40 years from the aspects of experiment, theoretical analysis and numerical simulation.   Result  On the basis of error field progress, we list the most concerned and unresolved problems in error field investigation in the world.   Conclusion  We expect that this paper will provide some guidance for further investigations on frontier problems of error field, and help to contribute our strength to the knowledge of magnetically confined fusion physics.
ITER Fusion Device and Its Power Supply System
Xingguang HU, Zhiquan SONG, Ge GAO, Hua LI, Peng FU, Hang LI
2022, 9(2): 19-25   doi: 10.16516/j.gedi.issn2095-8676.2022.02.002
[Abstract](34) [FullText HTML](5) [PDF 3770KB](6)
  Introduction  In order to realize controlled nuclear fusion and solve the future energy problems of mankind, International Thermonuclear Experimental Reactor (ITER) is planning to build a superconducting Tokamak device for fusion reaction.   Method  This paper briefly described the significance and development of ITER program and introduced the composition and function of its power supply system, as well as the structure and technical parameters of converter power supply of main coils.   Result  Finally, the optimization design of ITER magnet power supply in China and related procurement task for magnet power supply that have been completed are proposed.   Conclusion  By participating in ITER research projects, China has made important contributions to the development of international fusion engineering technology.
Research on the High Power Magnetic Field Immunity Test System for ITER
Xuesong XU, Ya HUANG, Hong LEI, Li JIANG, Jie ZHANG, Kun WANG
2022, 9(2): 26-32   doi: 10.16516/j.gedi.issn2095-8676.2022.02.003
[Abstract](19) [FullText HTML](7) [PDF 4092KB](1)
  Introduction  To ensure the safe and stable operation of the equipment, the power electronic equipment regulated by the International Thermonuclear Experimental Reactor (ITER) organization must pass the relevant magnetic field immunity test.   Method  Based on ITER requirements, the parameter requirements of the required test system were defined. Square solenoid coil and square three coil were selected as the research objects. The structural parameters of the optimal performance were calculated by numerical calculation method, and the correctness of the calculation was verified by finite element method.   Result  Compared with the two coil types, the solenoid with low power consumption is selected as the final structure. Then, based on this parameter, the power topology of DC transient is analyzed, the relevant parameters are calculated, and the performance data required by the final power supply is determined.   Conclusion  The research of this paper provides a detailed calculation process and design reference for the design of induction coil and its power supply of ITER high-power magnetic field immunity test system.
Research on Overall Design of Quench Protection System for CFETR
Qianglin XU, Hua LI, Zhiquan SONG, Meng XU, Xining ZHANG
2022, 9(2): 33-38   doi: 10.16516/j.gedi.issn2095-8676.2022.02.004
[Abstract](47) [FullText HTML](7) [PDF 2774KB](7)
  Introduction  The huge energy stored in the superconducting magnet in quench state is transferred and consumed by China Fusion Engineering Experimental Reactor (CFETR) quench protection system to prevent it from damage. In order to meet the design requirements of CFETR quench protection system, the overall design of the system is carried out in this paper.   Method  The basic principle and action logic of quench protection system were introduced, and the system design parameters of toroidal field coil (TF) quench protection unit and poloidal field / central solenoid coil (PF/CS) quench protection unit were described respectively.   Result  The two different schemes currently designed are analyzed. The topological structure and the switching logic of the quench protection switch, and the design requirements of other components are mainly introduced.   Conclusion  For the overall design scheme of the system, due to low cost, less land occupation, relatively mature technology and high feasibility, the mechanical DC switch with artificial current zero-crossing is the preferred scheme. Taking into account good prospects for development, hybrid DC switch with mechanical switch and solid-state switch is chosen as alternative.
Research on CFETR 110 kV Cable Grounding Scheme
Peng LI, Yuchen WANG, Jiafu JIANG, Yiyun HUANG
2022, 9(2): 39-44   doi: 10.16516/j.gedi.issn2095-8676.2022.02.005
[Abstract](123) [FullText HTML](36) [PDF 2204KB](22)
  Introduction  China Fusion Engineering Experimental Reactror (CFETR) aims to demonstrate the engineering feasibility of steady-state combustion plasma. The 110 kV high-voltage power supply and distribution system supplies the superconducting magnet and the reactive power system through cables and other equipment. Therefore, the stable work of the high-voltage cable is very important to the development of the experiment.   Method  The normal operation of the cable needs to consider the induced potential and circulating current of the metal sheath. In this paper, after fully investigating and calculating the metal sheathing method, it was determined that the 110 kV high-voltage XLPE cable was cross-connected and grounded. Use ANSYS Maxwell to model the three-phase cable, simulate the sheath induced voltage, and finally substitute the simulation results into the equivalent circuit constructed by Simplorer.   Result  The simulation results show that the induced electric potential and circulating current of the sheath meet the requirements of national standards.   Conclusion  The cross interconnection grounding scheme designed in this paper for the 110 kV cable sheath is safe and reliable, which can ensure the long-term stable operation of the cable.
Conceptual Design Technology Research of CFETR Fusion Power Plant
Kui XIANG, Zhanpeng LIANG, Hua LI, Guangtao ZHU
2022, 9(2): 45-52   doi: 10.16516/j.gedi.issn2095-8676.2022.02.006
[Abstract](21) [FullText HTML](6) [PDF 1044KB](3)
  Introduction  Based on the power output characteristics of China Fusion Engineering Experimental Reactor(CFETR) and under the condition of the maximum thermal power 1.25 GW, this paper aims to provide a conceptual design scheme of CFETR fusion power plant.   Method  To resolve the confliction between the periodic long pulse output characteristics of CFETR fusion reactor and the continuous stable input requirements of conventional island equipment, the energy storage technology scheme was adopted to realize the safe and stable operation of CFETR fusion power generation in the way of "peak cutting and valley filling" .We discussed energy storage under two different cladding schemes of CFETR fusion water cooling and helium cooling, as well as the combination scheme of coupling and decoupling operation modes between primary and secondary circuits. Through scheme comparison, the optimal energy storage operation combination corresponding to different cladding of CFETR fusion reactor was given.   Result  The results show that the best combination scheme of water-cooled cladding and helium cooled cladding fusion reactor is heat transfer oil + decoupled heat storage scheme and molten salt + coupled heat storage scheme.   Conclusion  From the conventional island side, compared with the water-cooled cladding scheme, the technical economy of CFETR fusion power plant with the helium cooled cladding scheme is better. The conceptual design scheme of CFETR fusion power plant has high reference value for the subsequent fusion power generation technology research and engineering design.
Applicability Analysis of Energy Storage Techniques for CFETR Fusion Power Plant
Zhanpeng LIANG, Kui XIANG, Hua LI, Guangtao ZHU
2022, 9(2): 53-62   doi: 10.16516/j.gedi.issn2095-8676.2022.02.007
[Abstract](14) [FullText HTML](6) [PDF 2659KB](2)
  Introduction  The power output of China Fusion Engineering Test Reactor (CFETR) is periodic, which can not directly meet the stable and continuous input requirements of conventional power generation equipment. CFETR fusion power plant needs to integrate a specific process system between nuclear island and conventional island.   Method  By investigating the application of concentrating solar power plants and the literature research of fusion power plants, this paper presented a discussion based on the preliminary performance of CFETR about the comparison between energy storage and energy supplement, energy storage techniques, thermal storage mediums and thermal storage system schemes.   Result  For fusion reactors with water-cooled blanket and helium cooled blanket, it is proposed to integrate an indirect double-tanks sensible thermal storage system with hydrogenated triphenyl heat transfer oil and solar salt molten salt as thermal storage medium respectively, so as to ensure the stable and continuous operation of the power generation system.   Conclusion  The proposed energy storage scheme meets the conditions of large-scale commercial applications and supports the overall design of CFETR fusion power plant.
General Layout Optimization for Fusion Power Plant
Xinkai LI, Kui XIANG, Hua LI, Guangtao ZHU
2022, 9(2): 63-69   doi: 10.16516/j.gedi.issn2095-8676.2022.02.008
[Abstract](25) [FullText HTML](4) [PDF 2949KB](9)
  Introduction  The general layout of the plant has great significance for the conceptual design process of the China Fusion Engineering Test Reactor (CFETR). Herein, preliminary exploration of the fusion power plant general layout has been conducted by comparing various energy storage system selection and planning energy storage area layout.   Method  This research analyzed the energy flow characters of the fusion power plant, energy storage technology route and the characteristics of heat storage materials. Techno-economic comparisons have also been given among four plans of various combination of heat storage methods and their layouts.   Result  We find that the molten salt storage solution has outstanding economic strengths, but its high temperature corrosion has a greater impact on the safety operation and maintenance of nuclear power plants, while the heat transfer oil solution is just the opposite. Therefore, the results show that triangular arrangement or tandem arrangement of energy storage areas with nuclear islands and conventional islands can well meet the thermal system of the whole plant and the thermal operation flow direction of the energy storage system, which is in line with the general layout requirements.   Conclusion  In conclusion, the energy storage technology route and the arrangement of the storage area are key factors affecting the layout of fusion power plants. The layout presented in this paper are all well adapted to the thermal operation of the newly added energy storage system that may be applied in the fusion power plant general layout.
Analysis of Harmonic Instability of Tokamak Power System Caused by Rectifier Transformer Bias
Jiansheng WANG, Huafeng MAO, Zhiwei MAO, Liuwei XU
2022, 9(2): 70-76   doi: 10.16516/j.gedi.issn2095-8676.2022.02.009
[Abstract](18) [FullText HTML](6) [PDF 1420KB](1)
  Introduction  The paper aims to effectively suppress the disturbance of non characteristic harmonics to the power grid in the Tokamak power supply system, the paper studies the mechanism of low-frequency harmonics in the Tokamak power supply system.   Method  By introducing an improved switching function model, selected ITER fusion device as an example and established its corresponding AC/DC equivalent circuit model combined with its corresponding parameters, the corresponding output second harmonic was obtained through calculation and simulation.   Result  The ratio of output to input is calculated, and the stability factor value almost tends to zero.   Conclusion  It is determined that the DC bias of rectifier transformer do not cause harmonic instability of the system.
Boundary Reconstruction of Tokamak Plasma Based on Deep Neural Networks
Jiayi LI, Shunping GU, Mengjun GU, Heng ZHANG, Rui SHA
2022, 9(2): 77-81   doi: 10.16516/j.gedi.issn2095-8676.2022.02.010
[Abstract](12) [FullText HTML](6) [PDF 1519KB](3)
  Introduction  In order to realize the real-time reconstruction of plasma shape and position in Tokamak, a visible light edge reconstruction algorithm based on fully connected neural network is proposed based on the analysis of camera calibration algorithm.   Method  The function of the algorithm was to establish the corresponding relationship between the pixel coordinate system and the To kamak coordinate system, and then realize the plasma visible light edge reconstruction.   Result  On the basis of the algorithm, few-shot learning is added to further improve the reconstruction algorithm of fully connected neural network.   Conclusion  Experimental results show that the algorithm can accurately reconstruct the plasma visible light edge, and also meet the real-time requirements of the system.
Optimization of High Uniformity Steady-State Magnetic Field Generator
Yan HE
2022, 9(2): 82-89   doi: 10.16516/j.gedi.issn2095-8676.2022.02.011
[Abstract](13) [FullText HTML](3) [PDF 4893KB](3)
  Introduction  To evaluate the anti magnetic interference ability of electrical and electronic devices, it is necessary to carry out the corresponding magnetic field immunity test, in which the high uniformity steady-state magnetic field generator is the core component of a steady-state test device.   Method  Taking the conventional Helmholtz and Maxwell square coil as the research object, the parameters were optimized through numerical calculation, and the coil structure that can produce high-performance magnetic field was obtained analytically. The finite element method was used to establish a model for calculation, and the correctness of the results was verified.   Result  The general calculation formula of coil parameters is obtained through numerical analysis, and the two coil types are compared. The optimized Maxwell square coil with small size and power consumption is selected as the final structure.   Conclusion  The research of this paper provides a detailed calculation process and design reference for the high uniformity steady-state magnetic field generator, and can provide a theoretical basis for the design of corresponding equipment in the electrical industry.
Research on Civil Structure Design of Main Building for Fusion Power Plant Conventional Island
2022, 9(2): 90-94   doi: 10.16516/j.gedi.issn2095-8676.2022.02.012
[Abstract](17) [FullText HTML](3) [PDF 1421KB](4)
  Introduction  Using nuclear fusion to generate electricity is a promising way for nuclear energy in the future. In order to research the best civil structure design, it is necessary to discuss techniques from fossil fuel power plant and conventional island of other NPPs.   Method  Through comparation analysis, structure system of main building, roof structure, TG foundation and fire protection design were discussed.   Result  Conceptual design for civil structure and engineering advice are also given.   Conclusion  The research in this paper can provide reference for similar project.
Nuclear Power Generation Technology
Verification of Advanced Secondary Passive Residual Heat Removal System Based on Full-Scope Simulator
Jinchao LIU, Tongsheng WANG, Yaozu LIN, Heng ZHANG, Rui SHA
2022, 9(2): 95-100   doi: 10.16516/j.gedi.issn2095-8676.2022.02.013
[Abstract](10) [FullText HTML](4) [PDF 1796KB](4)
  Introduction  As an important design improvement to cope with the station black out (SBO) accident, the advanced secondary passive residual heat removal (ASP) system is based on the closed natural circulation of secondary side of the steam generator (SG), can effectively remove the residual heat of the reactor core in the case of total loss of feedwater.   Method  Based on Full-scope Simulator (FSS),the paper introduced the SBO superimposed SBO diesel engine failure and ASG pneumatic pump failure accident conditions on the simulator platform , and verify the influence of the ASP system for the primary and secondary loops of nuclear plants in accident conditions by using the simulation method.   Result  The simulation results we obtained demonstrate that after the ASP system was put into operation, the residual heat of the core was effectively removed. After 4 hours , the water level of the SG recover to 8.6 m, the pressure of the SG dropped to 1.2 MPa(a), the core outlet temperature dropped to about 209 ℃, and the margin of core saturation temperature is greater than 20 ℃, there is no risk of meltdown of the core, and the accident is in a controllable state.   Conclusion  The ASP system meets the requirements of the design conditions, and can realize the long-term and effective removal of the residual heat of the reactor core.
Analysis of Double-Hold Fault in RGL System of CPR1000 Unit
Haibo JI, Maolin JING, Heng ZHANG
2022, 9(2): 101-106   doi: 10.16516/j.gedi.issn2095-8676.2022.02.014
[Abstract](25) [FullText HTML](7) [PDF 1091KB](2)
  Introduction  The RGL system (Rod Position Indication and Rod Control System) is one of the important control systems in nuclear power unit, its performance is directly related to the availability of nuclear power unit when the double-hold fault happen in the RGL system, the entire control rod group will be locked, and the control rods cannot move in time during the transient test, load reducing operation or load raising operation of the unit, which may lead to the shut down of the reactor.   Method  Based on the experience feedback of the double-hold fault of the RGL system in a CPR1000 unit, this paper analyzed and researched the cause of the double-hold fault from the perspective of design principles.   Result  The analysis results indicate that the moment controller in the controller software misjudges the state of the MG rack, and thus outputs the wrong signal, which leads to the triggering of the double-hold fault.   Conclusion  Software defect is an important factor causing double hold fault of RGL system.
Research on Equipment Qualification for Pressure Transmitter Important to Safety of HPR1000
Peng GAO
2022, 9(2): 107-112   doi: 10.16516/j.gedi.issn2095-8676.2022.02.015
[Abstract](10) [FullText HTML](5) [PDF 831KB](3)
  Introduction  The pressure transmitter important to safety of nuclear power plant needs to pass the equipment qualification to confirm that it can perform the safety function under the accident condition. However, the current relevant standards do not explain the logic and mechanism of such equipment qualification, the rationality is not sufficient.   Methods  Based on the understanding of the identification system of electrical equipment important to safety at home and abroad, combined with the actual identification process of pressure transmitter important to safety of HPR1000, the identification theory of pressure transmitter important to safety was studied in detail.   Results  The important operating environment factors affecting its safety performance were analyzed, the significant aging mechanism was identified, the accelerated aging test was described based on the accelerated aging mathematical model, and the typical accelerated aging sequence and identification process of the safety-important pressure transmitter of HPR1000 was recommended.   Conclusion  The identification process can be used as a reference for the identification of safety-important pressure transmitters in China.
Review and Prospect of Localization of Reactor Coolant Pump for Export Nuclear Project
Feng WANG, Ming LÜ
2022, 9(2): 113-119   doi: 10.16516/j.gedi.issn2095-8676.2022.02.016
[Abstract](12) [FullText HTML](1) [PDF 919KB](6)
  Introduction  With the promotion of the "going out" strategy of China's nuclear power industry, the ability of independent supply of nuclear power equipment is more important for export of NPP. Especially in the context of the current Sino-US trade friction, the localization of core equipment is more required.   Method  Based on the successful achievement of localization of RCP for an international NPP Project exported by China, the route and method of localization of high-tech equipment was analyzed.   Result  As the most technically complicated main equipment of NI and also as export controlled dual-use item and replying on the rapid development of heavy equipment manufacturing in China, the localization of Reactor Coolant Pump (RCP) has been finally achieved for an international NPP project.   Conclusion  It broke down monopoly of the developed countries on supply of RCP, and solidified China's position as a great power of nuclear power equipment manufacturing. It also provided practical experience on design and production of high-tech equipment.
Feasibility Research in the Technology for Industrial Steam Supply by PWR Nuclear Power Plant
Yuzhen ZHANG, Baifeng LIAO, Jing WANG, Xiaojuan CHEN
2022, 9(2): 120-124   doi: 10.16516/j.gedi.issn2095-8676.2022.02.017
[Abstract](11) [FullText HTML](4) [PDF 1930KB](1)
  Introduction  The paper aims to research the technology feasibility of steam conversion system for industrial steam supply by pressurized water reactor (PWR) nuclear power.   Method  we took a 1 000 MW (PWR) nuclear power plant as an example, supplying industrial steam 300 t/h, 1.8 MPa and 250 ℃. This paper demonstrated the technical feasibility of a steam conversion system which could meet the industrial steam needs by using steam in the secondary loop of PWR nuclear power plant to heat industrial water, based on the first law and the second law of thermodynamics. This paper designed the process flow of the system, calculated the thermodynamic parameters of the key heat exchangers in the system.   Result  The reasonable value of the heat source drainage temperature was analyzed. Our data suggest heat source drainage temperature is 65 ℃ for the industrial steam supply of PWR nuclear power plants. The temperature of heat source would be lower than the industrial water if the drainage temperature was lower than 60 ℃ , which would violate the second law of thermodynamics.   Conclusion  The research results can provide technical reference for industrial steam supply of PWR nuclear power plant.
Development and Application of AP1000 Nuclear Power Plant Equipment Reliability Database
Tianzuo QU, Qishu FANG, Yanlong QIAO
2022, 9(2): 125-130   doi: 10.16516/j.gedi.issn2095-8676.2022.02.018
[Abstract](10) [FullText HTML](7) [PDF 943KB](2)
  Introduction  The important value of equipment reliability data in nuclear power plant PSA, RCM, maintenance rules, reliability assurance program, risk guide management and other fields, puts forward the necessity of developing AP1000 equipment reliability database.   Method  Some important issues in the development process of AP1000 nuclear power plant specific database, such as independent failure analysis process, equipment and equipment category selection, reliability parameter estimation method, common cause failure analysis method and process, nuclear power plant specific data and general data. The collection and analysis of nuclear power plant specific data and general data collection and analysis, as well as the application of reliability data, etc. were discussed.   Result  The technical route for the development of AP1000 power plant specific equipment reliability database was proposed.   Conclusion  The establishment and application of AP1000 nuclear power plant equipment reliability database can accumulate valuable nuclear power plant specific operation, maintenance, failure, test and other data, provide reliability parameters for nuclear power plant operation PSA, provide an important reference for optimize operation and maintenance, safety management and other fields.
Development and Application of UHMWPE Nozzle for Nuclear Power Plant
Shushan CHEN, Tingshen ZHANG, Sanping XIAO, Qiangtao LI, Minjiang FAN, Zhi LI, Junshan HE
2022, 9(2): 131-136   doi: 10.16516/j.gedi.issn2095-8676.2022.02.019
[Abstract](19) [FullText HTML](5) [PDF 1955KB](2)
  Introduction  The paper aims to develop a corrosion resistant and wearable ultrahigh molecular weight polyethylene(UHMWPE) nozzle in order to solve the nozzle erosion and corrosion problems of circulating water filtration system(CFI) which is nuclear safety grade 3 system in nuclear power plant.   Method  Through the test of important processing parameters, the nozzle manufacturing process was confirmed. In order to verify the wear resistance and hydraulic performance of the developed nozzle, the wear resistance test of the material was carried out and the scour test and hydraulic test using developed nozzles also have been done.   Result  Test results demonstrate that the UHMWPE nozzle has excellent wear resistance, which is much better than traditional materials. The UHMWPE nozzle can meet the needs of high-speed erosion of nuclear power plants, and its hydraulic performance can also meet the requirements of nuclear power plants.   Conclusion  The test results show that the performance of the UHMWPE nozzle is excellent. It has been used in the nuclear power plant for one and a half years, after continuous operation, no scour deformation and corrosion phenomena were found. Therefore, it is feasible to use it in the CFI system of nuclear power plant, which can replace the original imported nylon nozzle.