核动力工程

Development of Fuel Management Code for Aqueous Homogeneous Reactors

WANG Liangzi, YAO Dong, WANG Kan

2011, 32(2): 1-5.

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Abstract:
Fuel Management Code for Aqueous Homogeneous Reactors（FMCAHR） is developed based on the Monte Carlo transport method.FMCAHR has the ability of doing resonance treatment,searching for critical control rods height,and calculating the thermal hydraulic parameters,bubble volume fraction and burn-up.The main structure and development process of FMCAHR is introduced in this paper,and the verifi-cation shows that the computing results of FMCAHR are precise.

Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry

LIU Qingjie, WU Hongchun, CAO Liangzhi

2011, 32(2): 6-11.

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A statistical transport equation is presented in this paper to obtain the ensemble average k_eff for the binary stochastic media with random fissile pellets.Combined method of statistics and deterministics is proposed to directly solve the multiplying binary stochastic problem in 1-D spherical geometry.In the combined method,Monte Carlo sampling method is employed to determine the mean chord length of the stochastic system then deterministic S_N diamond difference,source iteration method is used to solve the statistical transport equation with eigenvalue.Test stochastic problems of different scattering ratio,different chord-path ratio and different number of random fissile spheres are constructed and compared with references and uniformly-distributed approximated cases.Results show that the mean value of k_eff for the given systems can be predicted accurately by the statistical equation in most given cases.

Analysis and Improvements of Module Incidental Interference Faults of Water Level Control System Pressurize NPP

HU Ping, ZHAO Fuyu, QUAN Yan, JIANG Botao

2011, 32(2): 12-15,29.

Abstract(24) PDF(1)

Abstract:
In Daya Bay nuclear power plant,there have been many times that the module used to value the water level outputs a small pulse interference when the pressurizer water level control system is in operation,and the interference exists only in analog storage operation module,which can directly impact the control of the water level of the pressurizer,causing the water level fluctuations and adversely affecting the safe operation of the reactor.This paper analyzes the module incidental interference faults of the water level control system of the NPP pressurizer from the point view of the system control and design of module hardware,and finds out the reasons by the system simulation experiment and power supply circuit test.It is suggested to further improve on the design of hardware loops,add more inductance and capacity to eliminate the interference.

Dynamic Model of Helium Turbine Cycle System

JIE Heng, WANG Jie

2011, 32(2): 16-19.

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The one-dimension flow and heat transfer models are built to simulate the components of helium turbine system,including the helium turbine model,compressor model,heat exchanger model,valve model,pipe model and shaft velocity model.The transient simulation code is established in MATLAB.The accident of loss of load and the transient of decreasing heat transfer capacity of the main heat exchanger by 5% are simulated,and important parameters like helium flow rate,temperature,shaft velocity,power rate and compressor surge margin are analyzed.The calculated results agree with the analyzed results.This shows that the present model can be used to simulate the dynamic process of helium turbine closed-cycle system.

Calculation Verification of Startup Method for Density Lock Based on PID Control

CHEN Wei, YAN Changqi, GU Haifeng

2011, 32(2): 20-24,80.

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For the Passive Residual Heat Removal System,basing on the self-equivalence startup process,and adding pump controlling system,the startup method for density lock based on PID control system is advanced,that is,after the valve in PRHRS opening,the pump speed is controlled basing on the temperature changing in density lock,and the cold-hot liquid interface is maintained in the density lock,which ensures the PRHRS depart from the primary loop.According to the one-dimensional equations,the controlling startup process for the density lock is numerically simulated,and it is shown that under the effect of controlling system,the pressure in two loops can become balance gradually to start up the density lock successfully by changing the primary loop flux.The method makes the restrictions less and successful ration bigger for density lock startup.

Effect of Performance of Zr-Y Alloy Target on Thin Film Deposition Technology

PAN Qianfu, LIU Chaohong, JIANG Mingzhong, YIN Changgeng

2011, 32(2): 25-29.

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Yttria-stabilized zirconia（YSZ） films are synthesized on corrosion resistant plates by pulsed bias arc ion plating.The arc starting performance and the stability of thin film deposition is explored by improving the uniformity and compactibility of Zr-Y alloy target.The property of Zr-Y alloy target and depositional thin films were measured with the optical microscope,scanning electron microscope,X-ray diffractometer.The result shows that the target with hot rolling and annealing has a good arc starting performance and stability of thin film deposition,and the depositional thin films made of Yttria and amorphous zirconia are homogeneous and compact.

Study on Characterization of Interaction Layer of U-Mo/Al-2Si

LIU Yunming, YIN Changgeng, SUN Zhanglong, CHEN Jiangang

2011, 32(2): 30-34.

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U-Mo Alloy fuel is the most promising LEU fuel that used for research and test reactors.In this paper,the diffusion and reaction behavior of U-Mo/Al-2Si is studied with the hot-pressing diffusion-couple method.The experiment is carried out in a vacuum furnace for 550～570℃ at 5～21h.The result shows that the interaction layer thickness is increasing with temperature augmenting and time prolonging.Rich in Si layer is formed in the U-Mo side with 47.4 at.% Si.From U-Mo side to Al-2Si side,U（Mo） content is decreased while Al is increased,and Si is decreased after biggest content in U-Mo side.The phase of U-Mo side is mainly（U,Mo）（Al,Si）₃,and Al side the phase is a mixture of（U,Mo）（Al,Si）₃ and UMo₂Al₂.The amount of UMo₂Al₂ is increased from U-Mo side to Al-2Si side.

Preparation and Performance of Radiation Shielding Functional Aggregate Based on High Barium of Sludge

DING Qingjun, HUANG Xiulin, SUN Hua, XU Ke, YANG Kun

2011, 32(2): 35-38.

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The high barium of sludge has been made into aggregate with low dissolution rate,high strength by high temperature calcinations;the form of existence of element barium after its melted inside the aggregate has been analyzed by using XRD and SEM techniques;the linear attenuation coefficients has been measured among the functional aggregates,basalt,and barite.The results show that the radiation shielding capacity of functional aggregate has been improved substantially compared with that of the basalt,but is equivalent to that of barite.

Evaluation of Vibration and Vibration Fatigue Life for Small Bore Pipe in Nuclear Power Plants

WANG Zhaoxi, XUE Fei, GONG Mingxiang, TI Wenxin, LIN Lei, LIU Peng

2011, 32(2): 39-43.

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The assessment method of the steady state vibration and vibration fatigue life of the small bore pipe in the supporting system of the nuclear power plants is proposed according to the ASME-OM3 and EDF evaluation methods.The GGR supporting pipe system vibration is evaluated with this method.The evaluation process includes the filtration of inborn sensitivity,visual inspection,vibration tests,allowable vibration effective velocity calculation and vibration stress calculation.With the allowable vibration effective velocity calculated and the vibration velocity calculated according to the acceleration data tested,the filtrations are performed.The vibration stress at the welding coat is calculated with the spectrum method and compared with the allowable value.The response of the stress is calculated with the transient dynamic method,with which the fatigue life is evaluated with the Miners linear accumulation model.The vibration stress calculated with the spectrum method exceeds the allowable value,while the fatigue life calculated from the transient dynamic method is larger than the designed life with a big safety margin.

Seismic Analysis on Integral Reactor System with Large-Scale Three-Dimensional Finite Element Method

JIANG Naibin, ZANG Fenggang, ZHANG Limin, ZHANG Chuanyong

2011, 32(2): 44-47,58.

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The seismic analysis on integral reactor system was performed with TSV code which is applicable for calculating the large-scale finite element model.Two different models were calculated respectively.Damping effect was considered in one model,and nonlinear contact in the other one.The number of freedom degree of either model was more than twenty millions.The typical results of time-history response to Operational Basis Earthquake（OBE） excitation were given based on these two models.The results of this paper are larger than those with two-dimensional simplified FEM,and the reasons of this phenomenon were presented.The feasibility of seismic analysis on integral large-scale threes-dimensional finite element model under existing hardware condition was demonstrated,so a new approach to dynamic analysis on integral complex equipments or systems in nuclear power plant was explored.

Fracture Analysis for Pressure Pipe Wrapped with Carbon-Fiber Reinforced Composites

LIU Jun, YAN Bo, LU Yuechuan, SUN Yingxue, JIANG Naibin, CHANG Xueping

2011, 32(2): 48-52,115.

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A coupled FEM/EFG numerical method is introduced to calculate the stress intensity factors（SIF） along the crack front of a cracked pressure pipe line wrapped with carbon-fiber reinforced composite material（CFRC）.Two types of crack shape,traverse through-wall crack and surface ellipse crack are considered respectively,based on which the effect of the CFRC sleeve length to the Stress Intensity Factors is numerically investigated.It shows that using the algorithm presented in this paper,the stress intensity factrs of 3D component can be calculated effectively,and the SIF of the cracked pressure pipe line repaired with CFRC decrease obviously,compared to the original cracked pipe without any repair.Better repair efficiency is obtained with the increase of the sleeve length,but when the length is increased to a certain value,the length increasing of the sleeve contributes little to the decrease of the SIF,therefore to the repair efficiency.

Simulation of Thermal-Hydraulic Behavior in Tight Lattice Rod Bundle

YU Yiqi, GU Hanyang, YANG Yanhua, CHENG Xu, WANG Xiaojun

2011, 32(2): 53-58.

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The turbulence air thermal-hydraulic behavior inside the center and wall channel in tight lattice bundles is investigated.The wall temperature,wall shear stress,bulk temperature,bulk velocity,turbulent kinetic energy and turbulent mixing rate are analyzed by comparing the computational results with experimental data.The results show the increase of the non-uniformity of the parameters in tight lattice and the discrepancy between the calculation and the experiment with the decrease of P/D,and a temperature maximum appears in the gap region.This should be taken into account in the design of the fuel assembly with tight lattices.It is necessary to take the circumferential heat conduction of the channel wall into consideration in the simulation.

Study on Motive Characteristic of Sliding Bubble Near Wall in A Vertical Narrow Rectangular Channel

XU Jianjun, CHEN Bingde, WANG Xiaojun

2011, 32(2): 59-62,85.

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Motive characteristic of sliding bubble is visually observed by wide side and narrow side of the narrow rectangular channel using high speed digital camera.The results show that the bubble departing from the nucleate site slides along the heated surface,the typical sliding bubble phenomenon for narrow rectangular channels is observed in low heat flux,and the sliding bubble shape is spherical,and the upstream contact angle of sliding bubble on the heated surface is almost equal to the downstream contact angle of sliding bubble on the heated surface.The increase of the sliding bubble velocity is quick at the initial moment,and the sliding bubble velocity exceeds the local liquid velocity at some time.As the time increases,the sliding bubble velocity is almost equal.The sliding bubble velocity increases with increasing the bubble diameter.The sliding bubble velocity increases with increasing bulk velocity,and the trend of increasing sliding bubble velocity in large bulk velocity is larger than that in low bulk velocity.

Enhancement of Pool Boiling Heat Transfer on Porous Surface Tube

LI Yong, YAN Changqi, SUN Licheng, LIU Jia

2011, 32(2): 63-67,90.

Abstract(37) PDF(0)

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In this paper,the pool boiling heat transfer characteristics of a machined porous surface tube are investigated experimentally,considering the boiling operating condition of passive residual heat removal exchanger.The experiments have been carried out with high-pressure saturated steam condensation in tube as heating source and the results show that the porous surface tube has a considerable boiling heat transfer enhancing ability: the porous surface tube can increase the boiling heat transfer coefficient about 68%~75% and the wall superheat decreases about 1.5℃;With the combined effect of condensation inside tube and boiling outside tube,the axial wall temperatures of heat transfer tube are neither uniform nor linear distribution,but represent some particular distribution characteristics.On the base of the experimental investigation,the enhanced mechanism of porous surface tube is also analyzed.

Research on Pressure-Drop Type Instabilities Between Different Parallel Vertical Rifled Tubes at Lower Mass Velocity

DENG Zhian, LUO Yushan, WANG Haijun, CHEN Tingkuan, WU Yuan

2011, 32(2): 68-71,85.

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An experimental study was carried out on the pressure-drop type instabilities of the two-phase flow of the parallel vertical rifled tube in the high-pressure vapor-water test loop.The comparision of the effects of two types of tubes on the two-phase flow instabilities have been conducted.The results show that with the increase of inlet pressure and mass flow rate,the boundary heat flux of pressure-drop type oscillations increases;the boundary dryness thresholds of pressure-drop type oscillations increase with the increase of inlet pressure.In addition,with the increase of mass flow rat,the boundary dryness thresholds of pressure-drop type oscillations are increased with rifled tube of Φ31.8 mm×6 mm,but first increased and then decreased for the rifled tube of Φ28.6 mm×5.8 mm.It is also found that the range of the boundary dryness thresholds and the periods of the oscillations of pressure-drop type oscillations for two types of tubes are similar.Under the same operation parameters,the rifled tube of Φ31.8 mm×6 mm is more stable.

Bubble Sliding Growth Phenomena and Mass Velocity and Heat Flux Effect on Sliding Bubble Growth

CHEN Deqi, PAN Liangming, YUAN Dewen

2011, 32(2): 72-75,136.

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A visual experiment is carried out with water as working fluid at higher system pressure to investigate the bubble growth in vertical narrow channel in this paper.It is found that the bubble growth is significantly restrained with the increasing of system pressure,resulting in obviously decrease in bubble size within the same growth time.Also the bubble growth time at nucleation point will be shortened notably with higher system pressure.The main bubble growing period is during bubble sliding,and the bubble will lift off and return to the heating wall periodically.Growth of sliding bubble would not be affected by mass flux and heat flux monotonously.

Experiment on Geysering Phenomena in Heating System

QI Zhanfei, TONG Lili, CAO Xuewu

2011, 32(2): 76-80.

Abstract(18) PDF(1)

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Experimental study on liquid periodically boils at different heating power and analysis the experimental phenomenon and data.A correlation is given to describe the relationship between the period of geysering and heating power.The result shows that the liquid periodically boils and various flow patterns alternately occur.The refilling of cooler liquid causes significant change of temperature and pressure in the system.The period of geysering decreases with the increase of heating power.The flowing in the system varies more greatly as well as the pressure and temperature of liquid.Furthermore,a correlation is given to describe the relationship between the period of geysering and heating power.

Research on Transient Operation Characteristics of Helium Gas Turbine by Simulation

MA Yunxiang, LI Dong, TIAN Zhaofei

2011, 32(2): 81-85.

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By setting up the lumped parameter mathematic models of HTGR helium gas turbine and compressor device,and using Matlab/Simulink to build the simulation models,the transient operation characteristics of startup process of helium gas turbine were studied.The simulation results give the operation curves for high pressure compressor,low pressure compressor,and some key curves of compressor outlet pressure,core inlet and outlet temperature,turbine power,compressor power and generator power changing with core power.The calculation results show that,in the startup process,the trends of these main parameter curves meet the design requirements,and the transient characteristics simulation results are reasonable.

Numerical Simulation of Flow Characteristics of Lean Jet to Cross-Flow in Safety Injection of Reactor Cooling System

WANG Haijun, WANG Weishu, HE Huining, LUO Yushan

2011, 32(2): 86-90.

Abstract(28) PDF(0)

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In the present work,a numerical simulation was performed to study the flow characteristics of lean jet to cross-flow in a main tube in the safety injection of reactor cooling system.The influence scope and mixing characteristics of the confined lean jet in cross-flow were studied.It can be concluded that three basic flow regimes are marked,namely the attached lean jet,lift-off lean jet and impinging lean jet.The velocity ratio V_R is the key factor in the flow state.The depth and region of jet to main flow are enhanced with the increase of the velocity ratio.The jet flow penetrates through the main flow with the increase of the velocity ratio.At higher velocity ratio,the jet flow strikes the main flow bottom and circumfluence happens in upriver of main flow.The vortex flow characteristics dominate the flow near region of jet to cross-flow and the mixture of jet to cross-flow.At different velocity ratio V_R,the vortex grows from the same displacement,but the vortex type and the vortex is different.At higher velocity ratio,the vortex develops fleetly,wears off sharp and dies out sharp.The study is very important to the heat transfer experiments of cross-flow jet and thermal stress analysis in the designs of nuclear engineering.

Progress in Investigations on Thermo-Hydraulic Characteristics of Ship Nuclear Reactors under Ocean Conditions

MA Jian, LI Longjian, HUANG Yanping, HUANG Jun, WANG Yanlin

2011, 32(2): 91-96.

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The thermo-hydraulic characteristics of ship nuclear reactors are very important to the safety and reliability of ship voyage under the ocean conditions.Therefore,many countries have carried out plentiful investigations.This paper is based on some Asia open literature of investigations on thermo-hydraulic characteristics of ship nuclear reactors under the ocean conditions,reviews and sums up those main progresses such as the method,contents and typical results in this field,analyzes their insufficiency,and puts forward advices on the future investigation based on the known research findings.

Application of Signal Analysis in Instability of Parallel Twin-Channel System under Ocean Conditions

GUO Yun, GONG Cheng, CENG Heyi, XIA Genglei

2011, 32(2): 97-102.

Abstract(28) PDF(0)

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Parallel-channel two-phase flow systems under ocean conditions suffer from very serious parallel-channel instability,depending on the inherent characteristics of each channel and operating conditions.The influences of ocean conditions on the instability of parallel channel are very intensive.The trajectory of mass flow is very complex.The traditional methods cannot analyze such curves effectively.In this paper,Fast Fourier Transformation（FFT） method is used to analyze the complex curve of mass flow.Based on this method the oscillation curve can be decomposed.Some basic motions and inherent characteristics can be shown by the decomposition.The accurate analysis of the influence of ocean conditions is achievable.The onset of inherent parallel-channel instability is also analyzed.

Correlation for Prediction of Growing and Detaching Bubble Contact Diameter on a Heating Wall

CHEN Deqi, PAN Liangming, HUANG Yanping

2011, 32(2): 103-106.

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Phenomenal and theoretical analysis on the evolution of bubble contact diameter during bubble growing is presented in this paper,and it was found that the bubble contact diameter is dependent on the bubble growth rate and bubble radius strongly.By analyzing the regarding experimental data published in the literature,the relation between dimensionless bubble contact diameter,and dimensionless bubble growth time is obtained;based on this relation,a correlation relative to dimensionless bubble growth rate and dimensionless bubble radius are proposed for prediction of bubble contact diameter.With proper values of coefficients,a_w and n_w,this correlation can well predict the bubble contact diameter data published in the literature,with an error within ±20%.

Analysis of Fabrication Process for AP1000 Passive Residual Heat Removal Heat Exchanger

GAO Yongjun

2011, 32(2): 107-111.

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This paper introduces the design parameters of the passive residual heat removal heat exchanger for American advanced passive pressurized water reactor（AP1000）,describes the fabrication process for the head,tubesheet,heat exchange tube,corrugated plate and support frame assembly of the heat exchanger,mainly in terms of material,forging,welding,and heat treatment,and also analyzes the crucial steps for the support frame assembling,tubesheet plate welding,tube penetration welding of C tube bundle,closure/head welding,heat treatment,hydraulic（pressure） test,and etc.in the process of heat exchanger assembling.

Analysis of Primary Coolant Pump Seal Water Distribution Influence to Chemical and Volume System Design

WANG Zhigang, LI Jun, LI Lijuan, LIU Jiang, WANG Xiaojiang

2011, 32(2): 112-115.

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The possible influences to Chemical and Volume Control System design caused by coolant pump seal water distribution are discussed.The essential reason is picked out in this paper.The temperature drop of charging flow at the regenerative heat exchanger outlet is calculated,and the feasible retrofits of the Chemical and Volume Control System are illustrated.The thermal hydraulic software Flowmaster 7.5 is employed to numerically investigate the possible capability of charging pump with different coolant pump seal requirements.

Design of Control System for Test Platform of Reactor Shutdown System’s Ball Dropping Valve

YAO Qixin, HE Xuedong

2011, 32(2): 116-119,131.

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The newly designed ball dropping valve for the reactor shutdown system is a nuclear safety class equipment,and its design needs to be verified through substantial experiments.The control system of the test platform for the ball dropping valve is built to control,survey and protect a testing prototype of the valve’s driving component,and also to provide the methods of data collection and design scheme verification during the test.A control scheme which consists of PLC,stepping motor and position indicator is proposed,the model selection,control principle design and system integration and upgrading have been conducted,and some control circuit and components to be used are fully tested.

Effect of Grid on Characteristics of Stratification Stability in Density Lock

WANG Shengfei, YAN Changqi, GU Haifeng

2011, 32(2): 120-123.

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The research of effect of grid on stratification stability in density lock is carried out,through the theoretical analysis and experimental observation on the flow field in density lock.The results showed that,the flow in density lock is eddy flow;eddy flow is limited to the top of stratification when the stratification exists;the eddy and stratification interacted with each other until equilibrium,there are more than one equilibrium points in density lock without grid,the stratification is hard to stabilize because it will transit to next equilibrium point easily,but it easy to reach stable with the grid,and the stratification interface will higher with grid than without grid because the grid enhanced the energy dissipation.

Evaluation on Aging State of NPP Canned Motor Pump Based on SVM

ZHANG Liming, ZHAO Xinwen, CAI Qi

2011, 32(2): 124-127.

Abstract(33) PDF(0)

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A new method for aging assessment of canned motor pump in nuclear power plants was given in the paper.In practice,it is difficult to do the aging assessment for this kind of pump for its complicated structure,lack of samples and aging data.In order to solve these problems,the Support Vector Machine（SVM） which had its own advantages of solving the classification and evaluation in the case of limited examples was applied in this new method.The assessment indices including two performance parameters,and two status parameters were selected.And then the indices grade model and code coding rules were established and used to evaluation the aging condition on SVM with different kernel function.The results show that the application of the SVM method in aging assessment of canned motor pump is effective and reliable,especially with RBF kernel function that can get faster calculation speed,high generalization capability and more exact result.

Economy Analysis on Vertical Layout of Conventional Island of Nuclear Power Plant

WANG Xuefeng, LIU Jinwei, LIU Xiaoyun

2011, 32(2): 128-131.

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This paper briefly introduces the aboveground layout scheme and integral sinking layout scheme of conventional island of nuclear power plants.Technological-economic analysis formula are given,as a result,main factors influencing scheme selection is obtained.Determination of the layout scheme selection and optimization direction through the curve between the accumulative NPV and related factors is brought forward.The paper carries out the technological-economic comparison to the two schemes referred to a 1000MW level nuclear power project as the example,getting the curve between the accumulative NPV and the plant ground elevation,and offering the method of selecting the vertical layout scheme of conventional island and vertical layout optimization direction.

UML-Based Workflow Modeling of Behavior of Nuclear Power Plant Operators

GAO Wenyu, ZHANG Li

2011, 32(2): 132-136.

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The property of behavior of nuclear power plant operators is analyzed by the unified modeling language,based on which a method of workflow modeling for behavior of operators is proposed.This work-flow model can be used to analyze the reliability of operators.Workflow model not only describes the proper-ties and constraints of behavior of operators exactly and visually,but also analyzes the behavior of operators from many different angles,such as workload,resource utility,control flow optimization,and etc.Two typical events are used to describe the proposed modeling method.

Study on Application of Tri-sodium Phosphate in Containment Spray System

WANG Lin, DUAN Yongqiang, CUI Huaiming

2011, 32(2): 137-140.

Abstract(24) PDF(0)

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Trisodium phosphate（TSP） belongs to strong acid-weak base salt,having the strong alkalescence,good solubility and steady chemical property.It can be preserved for a long time.In order to provide the effective trapping of iodine in the water and to prevent the stress corrosion cracking of the metal material,it is necessary to buffer the acid and raise the pH by the addition of trisodium phosphate in the spray water.We have studied TSP application in EAS system through the calculation of TSP quantity,and the ability to adjust pH and dissolution time.The structure and the layout of TSP storage tank could be confirmed.It is concluded that the setting of TSP container beside the containment sump,sodium hydroxide could be replaced by trisodium phosphate.

Application of High-Strength Non-Shrink Cement Based Grouting Material in Nuclear Power Installations

LI Zhong, ZUO Weiwei

2011, 32(2): 141-144.

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This paper briefly describes the related technical requirement of secondary grouting during the process of equipment installation in nuclear power projects.The method and procedure are introduced in detail from the aspects of acceptance,preparation,pouring,collecting and maintenance of the high-strength non-shrinking based pouring cement material,and the cautions during the construction is also provided.The factors affecting the quality of the field grouting is analyzed,and the measures to reduce or eliminate the micro-cracks during the process is provided.

2011 Vol. 32, No. 2