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2016 Vol. 37, No. S2

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Seismic Analysis of Structure under Influence of Fluid
Tan Tiancai, Gao Lixia, Ma Jianzhong
2016, 37(S2): 1-3. doi: 10.13832/j.jnpe.2016.S2.0001
Abstract(51) PDF(0)
Abstract:
The complete finite element model of reactor inernals of a certain type test reactor including grid plate assembly and core component is established. Modal combination method of CQC is adopted for the spectrum analysis of the reactor internals. Effect of added mass in still water on the transverse v...
Analysis of Weld Overlay Residual Stress for Dissimilar Metal Welds in Qinshan Nuclear Power Plant
Zhang Shiwei, Chen Xuede, Zhang Yong, Sun Lei, Li Xihua
2016, 37(S2): 4-6. doi: 10.13832/j.jnpe.2016.S2.0004
Abstract(65) PDF(2)
Abstract:
Alloy 82/182 were used extensively in PWR primary coolant system as the DMW weld structure for the pipe nozzle and pipelines. The dissimilar metal welds(DMW) easily appears cracking due to the stress corrosion and fatigue after long operation. Based on the service data from foreign nuclear powers, t...
Decoupling Solution and Verification of Free Vibration Equation of Curved Beam
Li Xingzhao, Li Pengzhou, Sun Lei
2016, 37(S2): 7-10. doi: 10.13832/j.jnpe.2016.S2.0007
Abstract(50) PDF(0)
Abstract:
Based on Euler-Bernoulli beam model, this paper establishes the differential equation of arc-curved beam in the free vibration state, and the decoupling solution is theoretically derived, and verified with FEM method. The results show that the modal frequency results of the theoretic method differ f...
Crack Growth Analysis of Ω Seal Overlay Weld Repair for CRDM
Luo Jiacheng, Zhang Yong, Li Pengzhou, Luo Juan, Sun Lei
2016, 37(S2): 11-13. doi: 10.13832/j.jnpe.2016.S2.0011
Abstract(47) PDF(0)
Abstract:
The Control rod drive mechanism(CRDM) is a key device in the nuclear reactor, and the pressure shell of CRDM is installed on the canopy of the reactor pressure vessel by the Ω seal weld. The primary water stress corrosion is the major factor for the cracking of Ω seal weld, resulting in the leakage ...
Three Key Mechanical Problems of Flow Induced Vibration of Tube Bundles in Two-Phase Flow
Jiang Tianze, Li Pengzhou, Ma Jianzhong, Gao Lixia, Lai Jiang
2016, 37(S2): 14-19. doi: 10.13832/j.jnpe.2016.S2.0014
Abstract(50) PDF(0)
Abstract:
The tube bundle of heat exchange apparatus may generate flow induced vibration(FIV)under the fluid force. Excessive FIV can cause damage to the heat exchanger components, especially the U-bend section of the nuclear steam generator in two-phase flow. Because of the complexity of two-phase flow and c...
Vibration Characteristics of a Core Barrel with Conventional and Unconventional Core Support Barrel
Lai Jiang, He Chao, Xi Zhide, Sun Lei, Li Pengzhou
2016, 37(S2): 20-23. doi: 10.13832/j.jnpe.2016.S2.0020
Abstract(32) PDF(1)
Abstract:
The flow-induced vibration(FIV) of the core barrel is very common, and the characteristics of the FIV is important to the security of the nuclear reactor. By monitoring the vibration characteristics of the core barrel, the natural frequencies of the core barrel would decrease, as the nuclear reactor...
Study on Flow-Induced Vibration for Pipe Conveying Fluid Based on Two Way Coupling Method with CFD and FEM
Liu Guixiang, Zhang Kun, Lin Song
2016, 37(S2): 24-27. doi: 10.13832/j.jnpe.2016.S2.0024
Abstract(54) PDF(0)
Abstract:
The two way coupling numerical model for a typical pipe conveying fluid is established based on two way coupling method with CFD and FEM, and the dynamic characteristics of flow-induced vibration are obtained. The effects of flow velocity, stiffness and location of pipe supports on its flow-induced ...
Analysis of Flow-Induced Vibration of Nuclear Reactor Internals
Lai Jiang, Yang Jie, Xi Zhide, Sun Lei, Li Pengzhou
2016, 37(S2): 28-31. doi: 10.13832/j.jnpe.2016.S2.0028
Abstract(52) PDF(1)
Abstract:
The flow-induced vibration characteristic of a new nuclear reactor was analyzed in this paper by performing dynamic test and numerical calculation. A 1/2 scaled-down model of a new designed nuclear reactor was manufactured for performing the dynamic test with the hydrodynamics simulation system at t...
Analysis Method for Flow-Induced Random Load of Reactors
Lin Song, Liu Tianyan, Zhang Kun, Xie Xiaoyi
2016, 37(S2): 32-36. doi: 10.13832/j.jnpe.2016.S2.0032
Abstract(46) PDF(0)
Abstract:
Due to the complexity of flow induced vibration in reactors, previous studies mainly focused on the experimental research. Based on the analysis of the random responses of core structures excited by fluctuating pressures, the fluctuating pressures is obtained experimently by scale model. The theoret...
Study on Flow Induced Vibration in Reactor Internals of HPR1000
Yang Jie, Xi Zhide, Yu Danping, Ma Jianzhong, He Chao, Tan Tiancai
2016, 37(S2): 37-39. doi: 10.13832/j.jnpe.2016.S2.0037
Abstract(59) PDF(5)
Abstract:
The flow induced vibration is studied in this paper by the combined methods of experiment and simulation. Based on the similarity criterion for the flow induced vibration, a 1:5 test model is designed. According to the RG1.20, the experiment study and analysis and calculation are conducted by finite...
Research of Flow Induced Vibration Test for CAP1400 Reactor Internals
Xu Jing, Liu Linlin, Yu Danping, Ma Jianzhong, Li Xihua
2016, 37(S2): 40-43. doi: 10.13832/j.jnpe.2016.S2.0040
Abstract(61) PDF(0)
Abstract:
Referring to the CAP1400 reactor, the test model was constructed with a linear reduced scale of 1/6. FIV test of CAP1400 reactor internals have been done under all kinds of conditions, and complete data is obtained. According to FIV test results, it can be concluded that the design of CAP1400 reacto...
Test Studies of Flow Induced Vibration for Fuel Assembly
Zhang Xiaoling, Li Tianyong, Ma Jianzhong, Liu Litao, Li Pengzhou
2016, 37(S2): 44-46. doi: 10.13832/j.jnpe.2016.S2.0044
Abstract(45) PDF(0)
Abstract:
Test method is used to research fuel’s natural characteristics and flow induced vibration responses. It obtained the natural frequencies, and responses rule that is flow induced vibration responses increased with flow increases. Then it achieved waterfall for amplitude, frequency and time(flow) on t...
Review of Experimental Research of Flow-Iinduced Vibration of Reactor Internals
Yu DanPing, Ma Jianzhong, Xi Zhide, Yang Jie
2016, 37(S2): 47-51. doi: 10.13832/j.jnpe.2016.S2.0047
Abstract(48) PDF(3)
Abstract:
This paper reviews the experimental research of flow-induced vibration(FIV) of several reactor structures completed in recent years, such as FIV test of reactor internals of Qinshan Phase Ⅱ, 1:5 model FIV test of reactor internals of ACP1000, and comprehensive vibration assessment plan for HPR1000 r...
Analysis of Dynamic Characteristics Test for Reactor Internals
Xu Jing, Yu Danping, Ma Jianzhong, Li Xihua
2016, 37(S2): 52-55. doi: 10.13832/j.jnpe.2016.S2.0052
Abstract(39) PDF(0)
Abstract:
In this paper, testing principle, testing method, testing measurement system, and testing result have been introduced. According to the result, it can be concluded that the result of the test is reasonable and believable.
Study on Dynamic Characteristics of Extension-Type Fuel Assembly
Zhang Xiaoling, Zhao Hui, Yu Danping, Liu Litao, Sun Lei, Ma Jianzhong
2016, 37(S2): 56-57. doi: 10.13832/j.jnpe.2016.S2.0056
Abstract(42) PDF(0)
Abstract:
Numerical analysis combined with test which adopting impacting method is used to achieve the dynamic characteristics of fuel assembly under different boundaries. Firstly, finite-element analysis method is used to predict the natural frequency of fuel assembly, and the results supply a reference for ...
Exploration of Seismic Qualification Test Method for Nuclear Safety Class Valves
Li Qi, Li Pengzhou, Du Jianyong, Li Tianyong, Sun Lei, Li Pengfei
2016, 37(S2): 58-61. doi: 10.13832/j.jnpe.2016.S2.0058
Abstract(45) PDF(1)
Abstract:
Seismic qualification test must be conducted for the valves which are used in the nuclear power stations. When the valves are qualified for the seismic qualification in the first time, the test method is available. Among the existence criterions of the seismic qualification for valves, the seismic q...
Construction of Database on Nuclear Equipment Qualification Analysis and Test Data
Liu Linlin, Li Pengzhou, Li Qi, Li Pengfei
2016, 37(S2): 62-64. doi: 10.13832/j.jnpe.2016.S2.0062
Abstract(64) PDF(0)
Abstract:
Employing Oracle database program, following the basic table design based on the third paradigm, a database on nuclear equipment qualification analysis and test data was constructed. The establishment of the database using the index, partition, SQL optimization methods is able to efficiently integra...
Research on Vibration Issue due to Pipe Orifice Cavitation
He Chao, Lai Jiang, Yan Junming, Xi Zhide, Yuan Shaobo, Sun Lei
2016, 37(S2): 65-69. doi: 10.13832/j.jnpe.2016.S2.0065
Abstract(71) PDF(4)
Abstract:
The vibration issue due to pipe orifice cavitation of NPP containment spray system(EAS) is analyzed combining the field vibration test and numerical simulation analysis method. The study finds that pipe orifice plate choking leads to the emergence of cavitation downstream of the orifice plate, which...
Study on Seismic Test of CAP1400 Control Rod Drive Line
Li Qi, Li Pengzhou, Li Xihua, Sun Lei, Du Jianyong, Li Tianyong, Xie Yongcheng
2016, 37(S2): 70-72. doi: 10.13832/j.jnpe.2016.S2.0070
Abstract(41) PDF(0)
Abstract:
The seismic test of CAP1400 control rod drive line was conducted on the multiple point excitation test device. The horizontal direction and vertical direction of the CRDL were excited with multi-frequency earthquake time history at the same time. The strain values and acceleration of test piece unde...
Status for Fretting-Wear Study of Nuclear Structural Components
Gao Lixia, Li Pengzhou, Lai Jiang, Ma Jianzhong, Xi Zhide
2016, 37(S2): 73-76. doi: 10.13832/j.jnpe.2016.S2.0073
Abstract(51) PDF(0)
Abstract:
Flow-induced vibration of steam generator tubes or fuel rods results in fretting-wear damage due to impacting and rubbing of the tubes against their supports or fuel rods against their grids. Tubes and fuel rods are working at high temperature and pressure. The damages should be bad for the safety o...
Vibration Evaluation of Small Bore Pipe in NPPs Based on Strain and Acceleration
Shen Shuangquan, Xu Yugen, Zhang Shiwei, Li Xin
2016, 37(S2): 77-79. doi: 10.13832/j.jnpe.2016.S2.0077
Abstract(48) PDF(1)
Abstract:
Small bore pipes, existing in a form of large quantities of instrument pipes, sampling pipes and vent pipes, often suffer mechanical vibration fatigue fracture. Vibration fatigue life is evaluated according to measured vibration stresses for GRE023 pipes in Unit 2 of Yangjiang NPP. Measured accelera...
Vibration Attenuation Design of Plate and Shell Support Structure
Lu Jun, Zhang Kun, Liao Kuai, Sun Lei
2016, 37(S2): 80-84. doi: 10.13832/j.jnpe.2016.S2.0080
Abstract(61) PDF(1)
Abstract:
The blocking mass, frame style structure and elasticity separated devices are imported to the plate and shell supports. Schematic designs of vibration attenuation are conducted and simulation model of both modified and primary support structures are constructed, then the vibration transmission chara...
Investigation on Vibration Analysis and Evaluation of Multispan Straight Pipes Based on Powerflow Method
Xi Wenbing, Li Pengzhou, Sun Lei, Zhang Kun, Lin Song
2016, 37(S2): 85-88. doi: 10.13832/j.jnpe.2016.S2.0085
Abstract(35) PDF(0)
Abstract:
Piping system is a complex structure with multi-supports, and it is difficult to evaluate the vibration isolation performance of the system with traditional methods. A beam-rectangular-plate model is used to analyze the vibration transmission characteristics of the piping system in this paper. Furth...
Vibration Control and Experimental Study of Pipes for Auxiliary System
Li Xin, Liu Tianyan, Lin Song, Zhang Kun
2016, 37(S2): 89-91. doi: 10.13832/j.jnpe.2016.S2.0089
Abstract(51) PDF(0)
Abstract:
Under the excitation of the pump, the pipes of auxiliary system for primary loop have a problem of excessive vibration, and when the vibration is transmitted to the installed base, it may result in serious troubles. To solve this problem, the study on piping vibration control of auxiliary system nee...
Experimental Study of Multi Frequency Vibration Absorber in Pipe System
Liu Tianyan, Li Pengzhou, Xi Wenbing, Zhang Kun
2016, 37(S2): 92-95. doi: 10.13832/j.jnpe.2016.S2.0092
Abstract(47) PDF(1)
Abstract:
As important engineering structures, the pipe system is widely used in the primary circuit of the reactor. According to the vibration and noise and safety problems in pipeline system, a new type of multi frequency vibration absorber is designed. And the effectiveness of DVA is validated through expe...
Research on Shock Stress Reduction Factor in Shock Stress Evaluation of Stainless Steel Piping
Chen Xuede, Liu Zicai, Zhang Kun, Lin Song, Li Pengzhou, Li Xihua
2016, 37(S2): 96-98. doi: 10.13832/j.jnpe.2016.S2.0096
Abstract(42) PDF(0)
Abstract:
To study the over conservative margin of shock stress reduction factor in stainless steel piping designed by elasto-plastic rules, a method is used by carrying out elastic and elasto-plastic calculations for stainless steel piping with scaled three kinds of independent loads of gravity, pressure and...
Active Control of Vibration with Line-Spectrum of the Blade Pump
Zhang Kun, Xi Wenbing, Li Pengzhou, Sun Hongling, Li Xihua, Liu Tianyan
2016, 37(S2): 99-102. doi: 10.13832/j.jnpe.2016.S2.0099
Abstract(47) PDF(0)
Abstract:
The control on vibraiton with line spectrum of the blade pump, which is a typical rotate pump, has become the research hotspot in the field of vibration and noise control. On the demand of reducing the periodic line spectrum vibration of the blade pump, this paper studied the method for the line spe...
Gap Stiffness Value Research in Transient Dynamic Analysis for Piping Model
Huang Wenhui, Li Pengzhou, Chen Xuede, Li Xihua
2016, 37(S2): 103-106. doi: 10.13832/j.jnpe.2016.S2.0103
Abstract(65) PDF(0)
Abstract:
Set up a geometry nonlinear finite element model consistent with experiment model to calculate shock response of piping under transient load with nonlinear transient dynamic time history method and made comparison between corresponding experiment data and numeric results. By way of this comparison, ...
Vibration Transmission Analysis of Pipe System for Nuclear Reactor System Based on Transmission Path Analysis Method
Zhang Kun, Peng Liang, Li Pengzhou, Lin Song
2016, 37(S2): 107-110. doi: 10.13832/j.jnpe.2016.S2.0107
Abstract(44) PDF(0)
Abstract:
The noise source identification, qualification and recognition of transmission path are the precondition of the vibration and noise control. In order to meet the engineering requirement of quantitative vibration contribution analysis, the transmission path analysis method was applied to the vibratio...
Numerical Simulation on Effect of Steam Velocity on Separating Property of Cyclone Separator
Li Yong, Huang Zhen, Yuan Dewen
2016, 37(S2): 111-115. doi: 10.13832/j.jnpe.2016.S2.0111
Abstract(45) PDF(0)
Abstract:
In the present paper, numerical simulation on separating process of cyclone separator used in the steam generator is performed under conditions of different steam velocity based on two-fluid model and Reynolds Stress Model. The effect of steam velocity on separation process of droplets is analyzed. ...
Experimental Study on Critical Heat Flux of Rectangular Channel under Condition of Single Plate Heater
Liu Liang, Zhang Yan, Xing Dianchuan, Huang Zhigang
2016, 37(S2): 116-120. doi: 10.13832/j.jnpe.2016.S2.0116
Abstract(53) PDF(2)
Abstract:
The experimental study on critical heat flux of narrow rectangular channel under the condition of single plate heater about upward flow carried on high temperature and high pressures thermal hydraulic test facility was introduced in this paper. The effect of thermal hydraulic parameters such as mass...
Theoretical Investigation on Thermal Hydraulic Characteristics of Boiling Two-Phase Sodium
Qiu Zicheng, Lan Zhike, Ma Zaiyong, Qiu Suizheng, Zan Yuanfeng, Xing Dianchuan, Li Yongliang
2016, 37(S2): 121-124. doi: 10.13832/j.jnpe.2016.S2.0121
Abstract(40) PDF(0)
Abstract:
Based on the experimental work, thermal hydraulic characteristics of sodium boiling are theoretically researched. The object of calculation is an annulus. Liquid sodium is considered incompressible while sodium vapor is considered compressible. Homogeneous flow model is used in the two phase region ...
Experimental Analysis of Steam Effect on Hydrogen Combustion in Severe Accidents
Wang Ying, Li Yong, Zan Yuanfeng, Tang Yueming, Zheng Hua, Xie Shijie, Zhang Zhen, Zhang Youjia
2016, 37(S2): 125-128. doi: 10.13832/j.jnpe.2016.S2.0125
Abstract(41) PDF(0)
Abstract:
This paper investigates the effect of steam concentration on hydrogen combustion in severe accident condition. By changing the initial concentration of steam, combustion temperature, peak pressure, flame velocity and burn-off rate are compared, and experimental results also are compared. These resul...
Experimental Research on Passive Residual Heat Removal System of Small Modular Reactor under SBO
Zhang Yan, Lu Xiaodong, Peng Chuanxin, Bai Xuesong, Zan Yuanfeng, Zhuo Wenbin, Yan Xiao
2016, 37(S2): 129-134. doi: 10.13832/j.jnpe.2016.S2.0129
Abstract(39) PDF(0)
Abstract:
Based on the design characteristics of the passive residual heat removal system(PRHRS) for small modular reactor, a scaled experimental facility of passive safety system CREST was constructed. A short-term residual heat removal experiment under the station blackout accident(SBO) was performed in the...
Parameter Sensitivity Analysis of Interface Momentum Transfer Model in Two Fluid Model
Zhang Junyi, Yan Xiao, Xiao Zejun, Huang Yanping, Xu Jianjun
2016, 37(S2): 135-141. doi: 10.13832/j.jnpe.2016.S2.0135
Abstract(73) PDF(0)
Abstract:
Parameter sensitivity analysis of the interface force model and/or its key parameters in the momentum transfer models was carried out with the framework of two-fluid model. The effect of the interface force model and/or its key parameters on the axial and radial distribution of two-phase flow parame...
Experimental Investigations on Interaction of Surface Catalyst and Thermal Hydraulics in Passive Autocatalytic Recombiner
He Yanqiu, Yan Xiao, Sui Xi, Huang Yanping, Zan Yuanfeng, Huang Zhen, Wang Yin
2016, 37(S2): 142-145. doi: 10.13832/j.jnpe.2016.S2.0142
Abstract(44) PDF(0)
Abstract:
An experimental investigation focusing on the interaction between surface catalytic reaction and thermal hydraulics is carried out. Analysis is conducted on the effects of different inlet velocities and hydrogen concentrations on the chemistry and thermal hydraulics. From the experiment results, it ...
Investigations on Startup Methods of Large LOCA Blowdown Simulation Experiments
Xing Dianchuan, Tang Ming, Wang Tao, Hou Fengwei, Zan yuanfeng, Huang Jun, Qiu Zicheng
2016, 37(S2): 146-149. doi: 10.13832/j.jnpe.2016.S2.0146
Abstract(61) PDF(0)
Abstract:
The large LOCA blowdown simulation experiment is usually needed for the purpose of the performance evaluation of containment sump strainer and downstream effect analysis. In this paper, large LOCA blowdown simulation experiment was conducted by double rupture discs combining with a pneumatic valve, ...
Experimental Research of Separate Effect on Containment Condensation Heat Transfer
Zhang YouJia, Yu Shimo, Zhang Zhen, Bai XueSong, Zan YuanFeng, Zhuo WenBin, Yan Xiao, Wang Ying
2016, 37(S2): 150-155. doi: 10.13832/j.jnpe.2016.S2.0150
Abstract(58) PDF(1)
Abstract:
The effect of condensation heat transfer ability of containment is one of the significant factors on passive safety system by removing residual heat from core. The experimental study of separate effect on the containment condensation heat transfer was conducted, based on the passive containment cool...