核动力工程

Analysis of Effect of Late Water Injection on RCS Repressurization

TAO Jun, CAO Xuewu

2011, 32(3): 1-5.

Abstract(20) PDF(0)

Abstract:
Effect of late water injection on RCS repressurization during high pressure severe accident sequence in a typical PWR was analyzed.As the results shown,late water injection could increase RCS pres-sure when RPV failed without RCS passive depressurization.Especially in the condition of opening one PORV,RCS pressure could reach high pressure limit when RPV failed and the risk of HPME and DCH was dramatically increased.Integrity of containment could be threatened.However,in the condition of RCS pas-sive depressurization induced by pressurizer surge line creep failure,RCS pressure could be decreased to very low level even only one PORV was opened and two trains of emergency core cooling were implemented.The risk of HPME and DCH was eliminated.The more PORVs were opened,the faster accident progression was and the earlier RPV failed.RCS pressure was a little higher when PRV failed if two trains of emergency core cooling was implemented comparing with the condition with only one train of emergency core cooling.However the time of RPV failure was obviously delayed.From the point of delaying RPV failure and pre-venting containment early failure of view,the optimized late water injection was opening threc PORVs and implementing two trains of emergency core cooling.

Assessment of In-Vessel Corium Retention in CPR1000

CHEN Xing, ZHANG Shishun, LIN Jiming

2011, 32(3): 6-9,24.

Abstract(16) PDF(1)

Abstract:
The In-Vessel corium Retention（IVR） strategy of Chinese 1000 MW class commercial pres-surized water reactor（CPR1000） is assessed by Risk-Oriented Accident Analysis Methodology（ROAAM）.Four representative severe accident scenarios are selected for the IVR assessment in this paper.According to four representative severe accident scenarios consequence calculated by the deterministic code combined with engineering judgment,the input probability distribution of the assessment is determined.Success probability of IVR from the viewpoint of thermal failure is then predicted using MOPOL code.MOPOL is a code devel-oped basing on the well known ROAAM frame and heat transfer model of corium.It is demonstrated that the success probability of IVR by Reactor Cavity Flooding in CPR1000 is potentially higher than 99%.Applica-tion of IVR strategy in CPR1000 is envisioned probable if a further more comprehensive risk-benefit evalua-tion conclusion is positive.

Study of Containment Over-Pressure Fragility Curve and Analysis of Opening Pressure for Containment Filtration and Exhaust System

LIN Jiming, CHEN Peng, ZHANG Shishun

2011, 32(3): 10-14.

Abstract(22) PDF(1)

Abstract:
Based on the results of international researches and design feature of CPR1000 containment,the fragility curve for CPR1000 containment is studied.The operation pressure to put Containment Filtration and Exhaust System（EUF） into service is proposed.With different operation pressures,the radiological con-sequences has been compared.The results show that the pressure threshold for EUF operation can increase to 0.71MPa（g） and the starting time of the EUF is delayed about 1day and the accumulated activity to the envi-ronment is also decreased definitely.

Analysis of Pressure and Impulse Distribution in the Case of Ex-Vessel Steam Explosion

HUANG Xi, YANG Yanhua, WANG Xi

2011, 32(3): 15-21.

Abstract(18) PDF(0)

Abstract:
In order to investigate the pressure distribution outside the vessel during the process of steam explosion including both the premixing stage and explosion stage,a three dimension multiphase fluid analysis code MC3D has been used based on the structural and environmental characteristics of the sever accident state of 1000 MW level PWR Ling’ao Nuclear Power Station Phase II with the consideration of both pressure variation and impulse variation.The results indicate that the process of premixing has a low level pressure variation with a long duration.On the contrary,the explosion stage creates a high level and sharp pressure peak which threatens the integrity of the reactor cavity structure.In addition,the mass of the melt-drop con-tacts the coolant all over the calculating cells has a significant effect regarding the magnitude of the impulse created by the steam explosion.

In Situ Measurement of Neutron Multiplication in Active Zone Components of Pole Shaped Critical Assembly

JIN Yu, LI Maohui, QIU Dong, YANG Chengde, ZHOU Jing

2011, 32(3): 22-24.

Abstract(24) PDF(0)

Abstract:
In order to verify the effectiveness of the safety margin preset for the empty-handed assembly in the design of active zone for the pole shaped critical assembly,the conservative experiment model is es-tablished to carry out the in situ measurement of neutron multiplication.By adding components of fission system one by one,the multiplication in this experiment is measured as 2.67,which is under the limit in GB15146.7-94.The experiment shows that the safety margin of active zone preset in the design is enough,and the critical safety can be insured in the empty-handed assembling.

Simulation on In-Containment Source Term and Virtual Accident Scene of Large-Break LOCA

XIAO Hongguang, ZHU Bo, ZHANG Fan

2011, 32(3): 25-28,42.

Abstract(27) PDF(0)

Abstract:
The variation of the concentrations of aerosol ¹³¹I,airborne ¹³⁷Cs and ¹³³Xe under 3 different disposal measures,i.e.,without spray and emergency ventilation,with spray but without emergency ventilation,and with spray and emergency ventilation,was analyzed after a large-break LOCA for the small-scale experiment reactor.The results showed that the spray played an effective role in reducing the radioactive concentration of ¹³¹I and ¹³⁷Cs,but almost had no effect on the inert gas ¹³³Xe.Under the condition of this study,when the security system failed,the radioactive material would escape once the core melt.Finally,by the virtual simulation of the accident,the variation of the nuclide radioactive concentration in the whole containment was expressed intuitively in real-time and the combination of the accurate simulation data and the visual interface was achieved in this paper.

Study on Homemade Alloy used in SG U-Tubes of AP1000

LU Huaxing

2011, 32(3): 29-32.

Abstract(31) PDF(0)

Abstract:
This paper describes the application of alloy 690 in PWR nuclear power plants,as well as the main technical requirements and characteristics of alloy 690 tubes of AP1000 Steam Generators.Through different heat treatments and deformation process,this paper also studies the laws between chemical segregation,stable and continuous intergranular carbide precipitation and different process combinations.Test results indicate that the deformation extent and cooling speed after annealing have a great impact on the chemical segregation and the pattern of intergranular carbide precipitation.

Effect of Long-Term Aging on Electrochemical Corrosive Behavior of 17-4PH Stainless Steel

PENG Yanhua, WANG Jun, ZOU Hong, SHEN Baoluo

2011, 32(3): 33-37.

Abstract(22) PDF(0)

Abstract:
The corrosion and electrochemical behavior of long-term aging on 17-4PH stainless steel in different solutions has been measured by electrochemical methods.The solutions consisted of chlorine ion sulphuric acid and neutral.Electrochemical potention dynamic reactivation test.The polarization curves results demonstrate that the pitting potential of 17-4PH stainless steel shifted negatively and the protection performance of the passive film decreased after aging treatment.The decline of corrosion resistance of aged specimens,and with the age time prolonging corrosion inhibitors is decline the sulphuric acid can control the pit corrosion of 17-4PH stainless steel because the vitriol（S） can hold back the Cl^-,The anodic polarization curves illustrate that 17-4PH stainless steel can passive in 1% NaCl sulphuric acid,while in 1% NaCl neutral the passivity is deteriorated due to Cl-ion participate in electrochemical corrosion,accelerate the localized corrosion,destroy passivation and induce pit corrosion to the stainless steel.The decline of corrosion resistance of aged specimens was due to the precipitation of the second2 phase along grain boundaries and the transformation of microstructure.

Corrosion Products and Formation Mechanism of Hastelloy C-276 Alloy in Supercritical Water at 600℃

LI Haifeng, FAN Hongyuan, ZHANG Qiang, QIU Shaoyu, WANG Jun

2011, 32(3): 38-42.

Abstract(17) PDF(0)

Abstract:
The corrosion products of nickel-base alloy Hastelloy C-276 was investigated in supercritical water（SCW） at 600℃/25MPa through grazing incidence X-ray diffractometry,X-ray photoelectron spectroscopy and scanning electron microscopy,respectively.The results show that the uniform and complete oxide film was observed in SCW,which was identified to mainly consist of NiO,NiCr₂O₄,Cr₂O₃ and MoO₂;The oxide films that had duplex structure were in poor in Ni and Mo,but the inner layer was rich in Cr.The loose outer layer lacked of protective,while the compact inner layer was favor of antioxidation.The formation mechanism of corrosion products on alloy C-276 in supercritical water seemed to be similar to that in high temperature water.The Ni（OH）₂,NiO outer layer grew by dissolution and precipitation mechanism,while the Cr₂O₃ inner layer oxide was formed by oxygen diffusing inward and reacting with the retained Cr.

Finite Element Simulation for Equivalent Elastic Properties of Dispersion Fuel Elements

JIANG Xin, DING Shurong, HUO Yongzhong

2011, 32(3): 43-47.

Abstract(24) PDF(0)

Abstract:
The safety and reliability of the dispersion fuel elements in the reactors are the focus of relative researches.They depend on the mechanical property of the fuel elements.In the present work,several representative volume elements are chosen from the fuel elements according to the arrangement styles of the fuel particles in the matrix and the finite element analysis is applied to study the effective elastic property of the fuel element.The effects of temperature and volume fraction of the fuel particles on the property are investigated in details.As the particles are distributed randomly,the numerical results are compared with several analytical equations,and the comparison indicates that the Mori-Tanaka model provides the best agreement with the FEM data.

Effect of He on 12Cr-ODS Ferritic Steel Structural Damage during（He⁺+e^-） Dual-Beam Irradiation

HU Benfu, GUO Lina, JIA Chengchang, YANG Zhanbing, MU Xiabosi, GAO Qiaopingqilang, DU Bianjingyi

2011, 32(3): 48-51,72.

Abstract(24) PDF(0)

Abstract:
The 12Cr-ODS ferritic steel made by the method of sol-gel was prepared and effect of the interaction between point defects and He on the void swelling was studied by（He⁺+e^-） dual-beam irradiation.At the initial stage of irradiation,a lot of point defect clusters（dark dots） were nucleated.They grew slowly and their number density increased with irradiation dose and the clusters developed to interstitial loop.Also,fine void with high density were formed at different temperature and the void size increased slowly and the number density decreased slowly too with the increasing of irradiation dose.The resultant void swelling at each temperature after 15dPa were less than 0.05%.Thus this 12Cr-ODS ferritic steel showed excellent swelling resistance.The effect of interaction of point defect and He on the behavior of void swelling has been explained by the theory of irradiation damage in the present work.

Code Research on Mass Flux Assignment of Spuercritical Water-Cooled Reactor

LI Zhenyang, ZHOU Tao, SUN Canhui

2011, 32(3): 52-57.

Abstract(21) PDF(0)

Abstract:
Taking the fuel assembly of thermal spectrum supercritical water-cooled reactor（SCWR） as the research object,and on the condition of average orifice size,the reactor core power distribution is simulated,and the thermal hydraulic calculation model is established and the corresponding program is developed.The coolant mass flux distribution and related parameters distributions in the parallel channels is calculated.The results show that the axial density distribution and distribution core power of each fuel assembly group channels is very inhomogeneous,causing a large mass flux difference,which could be resolved through in-creasing the orifice size of high power fuel assembly groups.

Numerical Simulation of Flow Field in Cooling Tower of Passive Residual Heat Removal System of HTGR

LI Xiaowei, ZHANG Li, WU Xinxin, HE Shuyan

2011, 32(3): 58-62,72.

Abstract(17) PDF(0)

Abstract:
Environmental wind will influence the working conditions of natural convection cooling tower.The velocity and temperature fields in the natural convection cooling tower of the HTGR residual heat removal system at different environmental wind velocities were numerically simulated.The results show that,if there is no wind baffle,the flow in the cooling tower is blocked when environmental wind velocity is higher than 6 m/s,residual heat can hardly be removed,and when wind velocity is higher than 9 m/s,the air even flow downwards in the tower,so wind baffle is very necessary.With the wind baffle installed,the cooling tower works well at the wind speed even higher than 9 m/s.The optimum baffle size and positions are also analyzed.

Investigation on Characteristics of Bubble Growth and Effect of System Pressure on Bubble Growth

CHEN Deqi, PAN Liangming, YUAN Dewen, HUANG Yanping

2011, 32(3): 63-67.

Abstract(24) PDF(0)

Abstract:
In order to analyze the effect of system pressure on bubble growth in a narrow channel,a visual investigation on bubble growth under different system pressure（0.1-1 MPa） in a vertical rectangular narrow channel with 2 mm gap was carried out using the high speed camera.It was found that the bubble was growing at the nucleate site under 0.1-0.3 MPa system pressure;while it was sliding along the heating wall during growing under higher system pressure（p_s≥0.6 MPa）,and the size was much smaller.The heat transfer on the heating wall is obviously different due to different bubble behavior under different system pressure.After non-dimensionalization of bubble radius and bubble growth time with Laplace number,La,and time factor,ξ,respectively,the dimensionless bubble growth curve fits the power curve very well,and the coefficient k of the power curve decreases with the increasing of the system pressure.

CFD Method Research on Characteristic Cells in Rod Bundle Fuel Assembly

CHEN Jie, CHEN Bingde, ZHANG Hong

2011, 32(3): 68-72.

Abstract(18) PDF(0)

Abstract:
Two characteristic cells are in AFA-3G fuel assembly,that is typical cell and control rod guide cell.And there are some rules on the arrangement of mixing vanes.For the two characteristic cells,mixing capability is evaluated axially from the point of the first and second kind of sub-channel with CFD method.Mass mixing and heat mixing are interaction but different with each other.Although the mass mixing in the first kind of sub-channel is stronger,the thermal capability of the two is to some tune from the point of heat transfer.In the experiment research on thermal-hydraulic performance of AFA-3G fuel assembly,the arrangements of mixing vanes should refer to the two spacer grids of characteristic cells.

Study on Calculation Model of Onset of Nucleate Boiling in Narrow Channels

ZHANG Ming, ZHOU Tao, SHENG Cheng, FU Tao, XIAO Zejun

2011, 32(3): 73-76.

Abstract(23) PDF(0)

Abstract:
In the reactor engineering,narrow channels was used widely for its high power density,exceptional heat transfer and actual engineering requirements.The point of Onset of Nucleate Boiling（ONB） is the key point of boiling heat transfer in narrow channels.The point of ONB can directly influence the fol-lowing flow and heat transfer characteristics in the reactor.Due to the special structure and complexity flow,the point of ONB in narrow channels are effected by many factors,which characteristics are not understood completely yet.Using B＆R model,Su Shun-yu model,Pan Liang-ming model and Yang Rui-chang model,the heat flux of onset of nucleate boiling is compared and analyzed by taking water as the medium.And then the relationships of the heat flux with pressure,mass flow and wall temperature are obtained.Based on the differences of each model,the mechanisms for the main influence factors are suggested..

An Investigation of Bubble Slipping Characteristics of Subcooled Flow Boiling in Narrow Rectangular Channel

YUAN Dewen, PAN Liangming, WEI Jinghua, HUANG Yanping

2011, 32(3): 77-81,101.

Abstract(23) PDF(0)

Abstract:
The sliding bubbles in the vertical rectangular narrow channel were studied using visualization test section.It obtained the bubble sliding characteristics about the sliding distance changing with working conditions,and established the heat analysis model based on energy balance to research the impact of bubble sliding on the characteristics of heat transfer.Analysis showed that the bubble with sliding movement had a significant heat transfer enhancement than the bubble with fixed growth which did not slid.With the concept of disturbance intensity of sliding bubble proposed,it put up the heat flux expression caused by disturbance of sliding bubble and fixed bubble,and analyzed the difference between them.

Experiment of Density Wave Oscillation in Parallel Rectangular Channels

ZHOU Yuan, YAN Xiao, WANG Yanlin, LU Donghua

2011, 32(3): 82-86.

Abstract(21) PDF(0)

Abstract:
The test section consisted of two heated rectangular channels connected in parallel and paralleled by an unheated by-pass.Density wave oscillation in parallel rectangular channels was systematically observed on a two phase flow test rig operated at system pressures ranging from 1 to 10 Mpa.The oscillatory behavior is analyzed as well as the effects brought on the threshold of instability by changes in the operating system pressure,inlet subcooling number and mass flow.Moreover,this experimental data was compared with that inform the two parallel rectangular channels by using dimensionless subcooling number Nsub and phase change number Npch.The comparison indicates that the existence of by-pass makes the system more stable.

Effect of Heaving on Forces Acting on Bubbles in Heating Surface

HONG Gang, YANG Yanhua, LIU Xiangfeng, YAN Xiao, HUANG Yanping, CHEN Bingde

2011, 32(3): 87-91.

Abstract(12) PDF(0)

Abstract:
The effect of heaving on forces acting on bubbles in sub-cooled boiling flow has been analyzed.The buoyancy is directly affected by the heaving acceleration.And the flow rate fluctuation which is caused by the heaving acceleration imposes the forces acting on bubbles indirectly.The forces acting on bubbles under heaving and non-heaving condition have been computed and compared.The results show that heaving has less effect upon forced circulation than natural circulation.The influence of heaving upon natural circulation depends on flow rate fluctuation and the influence of heaving upon forced circulation depends on the weight of buoyancy in the balance of forces acting on bubble.Heaving influences the forces acting on bubbles,which may change the position of vapor bubble departure,hence affects the heat transfer in boiling flow.

Experimental Research on Single-Phase Heat Transfer Characteristics in a Vertical Circular Tube under Marine Conditions

DU Sijia, ZHANG Hong, JIA Baoshan

2011, 32(3): 92-96,101.

Abstract(24) PDF(1)

Abstract:
Experiments have been conducted to study the heat transfer characteristics of single-phase forced circulation when the test tube was under different marine conditions.The experiments measured the wall temperature of test tube to calculate the heat transfer coefficients at different circumferential places.When the test tube was under inclined conditions,the heat transfer coefficient increased at downside and decreased at upside of test tube because of buoyancy effect.When the test tube was under rolling conditions,the heat transfer coefficients fluctuated with the rolling motions,and the Coriolis force dominated the heat trans-fer fluctuation during the rolling motion.CFD method was used to simulate the heat transfer phenomena under marine conditions,and the results were accord to the experimental phenomena.

Analysis of Flow Characteristics under Flow Fluctuation Condition in Circular Channel

WANG Chang, GAO Puzhen

2011, 32(3): 97-101.

Abstract(22) PDF(0)

Abstract:
The experimental and numerical studies on the flow resistance characteristics under flow fluctuating conditions in a circular channel are carried out.The experimental results show that the pressure drop fluctuates with the same period of fluctuating flow rate;however,there is a phase lag between the two,and the phase lag in laminar flow is bigger than that in turbulent flow.In addition,the flow characteristics under the experiment conditions are numerically simulated based on the method of characteristic（MOC）.The simulation results are in agreement with experimental values.

Experimental Study on Friction Pressure Drop Characteristics of Simple Harmonic Pulse Flow Pole Point

JIA Hui, TAN Sichao, GAO Puzhen, YAN Changqi, HUANG Yanping

2011, 32(3): 102-105,126.

Abstract(30) PDF(0)

Abstract:
Friction pressure drop characteristics of the pole points of simple harmonic pulse flow were studied experimentally and theoretically.The comparison between the calculated results through the steady flow friction pressure drop empirical equation showed that the experimental friction pressure drops of crest point are lower than the calculated result,and the cases in trough point are opposite.The difference between the calculated and experimental data increased with the increase of pulse intensity（mean flow rate and pulse amplitude increasing,pulse period decreasing）.The velocity distribution of flow cross section of steady flow,crest and trough points were calculated,and the results showed that the increase of velocity grad along the diameter direction at trough point caused the increase of friction pressure drop.

Experimental Investigation on Resistance Characteristics of Two-Phase Flow through Porous Media Channel

ZHANG Nan, SUN Zhongning

2011, 32(3): 106-110,126.

Abstract(28) PDF(0)

Abstract:
Based on the new concept water-cooled packed bed reactor,the resistance characteristics of air-water flow upward through sphere-filled channel have been studied experimentally.The channels are packed with glass spheres of which the diameters are 2,5 and 8mm respectively.Experimental results show that the pressure drop increases with the increase of gas-liquid mass flow rate,and has a certain relationship with the flow patterns.The particle diameter and porosity have great influence on the pressure drop at the same flow condition.The published pressure drop correlations are grouped into two types（the separate flow model and the homogeneous model）.The two types of correlations are compared and modified,combined with 234 group experimental data.It is found that:（1） the best agreement between measured and calculated values is obtained with the correlations based on the separate flow model,but the predictive ability is reduced with the increase of particle diameter.（2） the existing homogeneous model show the considerable discrepancies with this experiment values,however the modified homogeneous correlation is in good agreement with the experimental data.

Condensing Behavior of a Freon Bubble with MPS-MAFL

LANG Minggang

2011, 32(3): 111-115.

Abstract(18) PDF(0)

Abstract:
In the study,MPS-MAFL is used to simulate the phenomenia of a Freon bubble condensing in a subcooled pool.The sensitivity on pool subcooling is also studied to understand the condensation behavior.The simulating shows that the bubble pressure decreases as the condensation begins with the shrinking of the interface.At the later phase of the condensation,the bubble pressure becomes larger than that of the circum-stance.A peak pressure will emerge at the moment that the bubble collapses and there will be a maximum pressure value at a certain subcooling.As the subcooling increases or decreases,the peak pressure will drop and may fade away.The maximum pressure is 3.12MPa at a subcooling about 20℃.

Stability of Cracked Cantilevered Pipes Conveying Fluid

CAI Fengchun, ZANG Fenggang, YE Xianhui

2011, 32(3): 116-121.

Abstract(26) PDF(0)

Abstract:
In this article,the equations of motion for the cracked cantilevered pipe conveying fluid is derived based on the extended Lagrange equations for systems containing non-material volumes.The virtual work done by the discharged fluid and that done by the fluid at the crack position due to the geometrical dis-continuity conditions are considered in the present equations of motion.There are geometrical discontinuity conditions at the crack’s location.The mode functions which satisfy the boundary conditions and geometrical discontinuity conditions are obtained by adding polynomial functions to the modal functions of the uncracked beam.The lowest three frequencies are computed and compared with results of the model for the cracked cantilevered pipes conveying fluid in existence.That shows the present derivations are reasonable.The stability of the cracked cantilevered pipes conveying fluid is studied and the effects of the crack on the eigenvalue branches which flutter occurs in are depicted.

Experiment of Bolt Stress in High Temperature and Pressure Vessel Head Installation

XIE Linjun, REN Xin

2011, 32(3): 122-126.

Abstract(26) PDF(0)

Abstract:
A large amount of scatter in bolt preloads is observed when bolting up a high temperature and pressure vessel head flange connection.In this study,a method to test the process and basic operation is pro-posed,by measuring the strain of bolt by stick to strain gage on the surface of a bolt;and a mathematical model of sine and exponential is designed to predict the scatter in bolt preloads,and thus to explore the appropriate of way on tightening.Experimental verification is provided for the validation of the mathematical model.Experimental and analytical results are presented and discussed.It is found that the stress of bolt meets the sine rule along the flange weeks;the single bolt meets the exponential decay law in the process of tightening.

A Case Diagnose of Loose Part for MCP Blade in TNPS Unit 1

LI Ruyuan, YANG Zhang, ZHOU Zhengping

2011, 32(3): 127-129,144.

Abstract(17) PDF(0)

Abstract:
An alarm event of loose part monitored by LPMS of unit 1 in TNPS was analyzed and diagnosed using the off line-analysis software of LPMS.The diagnosis conclusion was made that the events lied in or near by the main pump of loop 4 and the event was not a loosed part but may was a loosing part or dynamic to static friction.According to the overhaul suggestion,an inspect to the main pump of loop 4 and an explore to the bottom of pressure vessel were putted in practice in the time of T101 overhaul for unit 1,and it was found that a lamina of the impeller of the main pump of loop 4 was broken off and the lamina was found on the bottom of the pressure vessel.So the diagnosis was proved correctly.It shows that the effective moni-toring and the professional diagnosis to loose part play an important role in overhaul of nuclear power plant.

An Arithmetic for Core Physics Real-time Simulation Based on ADI

DING Xiaochuan, LU Haijin, ZHAO Qiang

2011, 32(3): 130-133.

Abstract(28) PDF(0)

Abstract:
In the core physics real-time simulation,the traditional Alternative Direction Implicit（ADI） method for solving the neutron diffusion equations requires too much calculation time to meet the real-time demand.In this paper,one fuel assembly is considered as one mesh-cell in radial direction to reduce the calculation time;the adjusting factor is added to the finite difference equations to improve the calculation accuracy.The calculation accuracy and speed are tested by its application to the core physics real-time simulation for Qin Shan NPP PHASE II.The simulation result shows that this approach is applicable for the core physics real-time simulation.With online correction technology,the online real-time simulation is accomplished.

Optimal Design of Condenser Weight

ZHENG Jing, YAN Changqi, WANG Jianjun

2011, 32(3): 134-138.

Abstract(19) PDF(0)

Abstract:
The condenser is an important component in nuclear power plants,which dimension and weight will effect the economical performance and the arrangement of the nuclear power plants.In this paper,the calculation model is established according to the design experience.The corresponding codes are also developed,and the sensitivity of design parameters which influence the condenser weight is analyzed.The present design optimization of the condenser,taking the weight minimization as the objective,is carried out with the self-developed complex-genetic algorithm.The results show that the reference condenser design is far from the best scheme,and also verify the feasibility of the complex-genetic algorithm.

Multi-Fields’ Coordination Information Integrated Platform for Nuclear Power Plant Operation Preparation

YUAN Chang, LI Yong, YE Zhiqiang

2011, 32(3): 139-144.

Abstract(19) PDF(0)

Abstract:
To realize the coordination in multi-fields’ work and information sharing,by applying the method of Enterprise Architecture（EA）,the business architecture,functional flow and application architecture of Nuclear Power Plant’s operation preparation information integrated platform are designed,which can realize the information sharing and coordination of multi-fields.

2011 Vol. 32, No. 3