核动力工程

Parameter Measurement of Thermal Neutron Beam in Thermal Column of Xi’an Pulse Reactor

LIU Shu-Huan, JIANG Xin-Biao, YU Qing-Yu, ZHONG Yun-Hong, ZHANG Wen-Shou, ZHANG Ji-Hong, YANG Jun, WANG Ying-Lin, WANG Kai, FANG Shao-Hui

2007, 28(4): 1-4.

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The distribution of the neutron spectra in the thermal column of Xi’an pulse reactor was measured with the time of flight method in this paper.Comparing with the thermal Maxwellian theory neutron spectra,the thermal neutron spectra measured in experiment is a little softer,and the average neutron energy in measurement spectra is about 0.042±0.01eV.The thermal neutron fluence rate at the front end of the thermal column,preliminarily measured with gold foil activation techniques,is about 1.18×10⁵cm^-2.s^-1.The standard uncertainty of the measured thermal neutron fluence is about 3%.

Research on Fuel Physical Characteristics in Small Long-Life Nuclear Power System

YU Gang-lin, WANG Kan

2007, 28(4): 5-8,38.

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Based on the simple introduction of recent development status of the long-life small nuclear burnup and a deep burnup core.The Program MCNP and MCBurn are used in the calculation of a Pin cell model with different initial driver fuels,p/d ratios,enrichments and fuel types to obtain some results for ex-power systems in the world,this paper puts forward a new concept of building a long-life reactor core with Thorium-Uranium fuel and Lead-Bismuth coolant and conducts a series of research on the characteristics of the Th-U fuel.In the physics design of a long-life reactor,it is important to keep a small reactivity swing with ample neutron spectrum,the reactivity swing with burnup and initial conversion ratio,etc.On the analysis of these results,this paper concludes some physical requirements of a long-life reactor core and constructs a core design with some safety parameters such as void reactivity coefficient and other results.

Core Physics Design Calculation of Mini-type Fast Reactor Based on Monte Carlo Method

HE Ke-yu, HAN Wei-shi

2007, 28(4): 9-12.

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An accurate physics calculation model has been set up for the mini-type sodium-cooled fast the basic physics characteristics of MFR can satisfy the requirement and objectives of the core design.The power density and neutron flux distribution are symmetrical and reasonable.The control system is able to make a reliable reactivity balance efficiently and meets the request for long-playing operation.reactor（MFR） based on MCNP-4C code,then a detailed calculation of its critical physics characteristics,neutron flux distribution,power distribution and reactivity control has been carried out.The results indicate that

Subchannel Analysis for Thorium-Based Advanced CANDU Reactor

WANG Song-tao, YU Ji-yang, LIAN Hai-bo, MAO Wen-long

2007, 28(4): 13-15,116.

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This paper presents the subchannel thermal hydraulic analysis in different thorium loading modes,different power and different lifetime using ASSERT-PVV3R1,a subchannel computer code developed by AECL,to determine the best loading mode from the point of view of subchannel thermal hydraulics.According to the results for subchannel the mass flux,void fracition and outset of dry power,a best loading mode is established from the point of view of being calm and security to power,i.e.,the loading mode of ThO₂ and SEU mixing in pellets is obviously better than the loading mode in which the only ThO₂ is loaded in the internal eight rods.

Development of MCNP Interface Code in HFETR

QIU Li-qing, FU Rong, DENG Cai-yu

2007, 28(4): 16-19.

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In order to describe the HFETR core with MCNP method,the interface code MCNPIP for HFETR and MCNP code is developed.This paper introduces the core DXSY and flow chart of MCNPIP code,and the handling of compositions of fuel elements and requirements on hardware and software.Finally,MCNPIP code is validated against the practical application.

Parallel Calculation Research on Monte Carlo Methodology

WANG Jia-chong, XU Chuan, YAO Dong

2007, 28(4): 20-24.

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Monte Carlo（MC） parallel calculation have been developed in nearly decades,which is taken an important role and a comparative advantage in particle transportation calculations.Considering the data initialization,the allotment of mission,the calculation reduce,the consistency of result and the function of program consistency,this paper compared the advantages and disadvantages of various calculations,and analyzed the difficulties encountered during the execution of the procedures.Ultimately the test and research results are shown.The results showed that MC calculation is with great efficiency for the particle transfer calculation.

Study of Shock Wave of Vapor-Liquid Two-Phase Mixture

ZHAO Liang-ju, WANG Fei, GAO Hong, TANG Jin-wen, YUAN Yue-xiang

2007, 28(4): 25-28.

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The paper studies the shock wave of vapor-liquid two-phase mixture,which is very important in a pressure-gain steam injector.The mathematic model is built and the calculation is done.After the shock the vapor is nearly condensed completely and the upstream Mach number and the volume ratio of vapor are the most important factors to the shock.We also find the similar characters of pressure and Mach number be-tween two-phase and single phase shock waves.The analysis of available energy shows that the shock process is an irreversible process with entropy increase.

Research Progress on Boiling Heat Transfer Mechanism of Sliding Bubble Near the Wall

XU Jian-jun, CHEN Bing-de, WANG Xiao-jun

2007, 28(4): 29-33,80.

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The research on the sliding bubble is increasingly received a great attention during the process of studying of the boiling heat transfer.The research on the sliding bubble is far from mature at present.The new research progresses on the heat transfer mechanism of the sliding bubble near the wall in recent years are summarized,and the sliding bubble dynamics and the heat transfer mechanism of the sliding bubble near the wall are discussed.The model of the heat transfer mechanism and the calculation methods on sliding bubbles are summarized.The contents on the sliding bubble dynamics required to further continuous study are presented,and the heat transfer mechanism model on the sliding bubble is constituted.Finally,the research direction on the sliding bubbles was suggested.

Test of Critical Heat Flux with Non-Uniform Axial Power Shapes in Rectangle Narrow Channel

XIONG Wan-yu, WANG Fei, XIAO Ze-jun, LU Dong-hua

2007, 28(4): 34-38.

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Critical heat flux for axial non-uniform heat flux distribution in rectangle narrow channel was studied in this report.During the test,electric heating were adopted,and the axial direction power loaded were truncation cosine distribution.The deionized water was heated.The test result indicated that CHF with non-uniform axial heat flux distribution was lower than CHF with uniform axial heat flux distribution.A correction factor was used to analyze the test data.The semi-empirical relation of correction factor of CHF with axial non-uniform heat flux distribution had been obtained.Comparing to the existing correction factor models,it revealed that the proposed semi-empirical relation predictive CHF with axial non-uniform heat flux distribution in rectangle narrow channel was most accurate.

Establishment and Validation of Boiling Pool Model in Fast Reactors

ZHAO Shu-feng, LUO Rui, WANG Zhou, SHI Xiao-bo, YANG Xian-yong

2007, 28(4): 39-43.

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The boiling pool in single subassembly is an important period in the severe accidental course of fast reactors,which may result in the propagation of molten UO₂ out of subassembly.To understand the mechanism of boiling pool clearly,the single-component mechanism model was established in this paper: the drift flux model was selected to predict the distribution of void fraction,and the temperature field and thickness of the fuel crust that encloses the boiling pool was obtained by solving the enthalpy model.According to the flow types,some modification was made on the Greene correlation.Results indicates that with the reducing of heat discharging ability of coolant,the boiling pool will be formed,and the imbalance between internal heat and outward heat transferring is the origin of vapor formation.The Greene correlation is fit for the molten pool before the generation of vapor.After the vapor is formed,the correlation should be modified according to the flow types.

Numerical Study of Non-Darcian Natural Convection in a Square Enclosure Filled with a Heat-Generating Porous Medium

WANG Gang, ZENG Min, WANG Qiu-wang

2007, 28(4): 44-48.

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Steady non-Darcian natural convection in a square cavity filled with a heat-generating porous medium is studied numerically by adopting the local thermal non-equilibrium model.The vertical walls maintain constant temperature T₀ while the horizontal walls are considered to be adiabatic.The flow field is modeled by using the Brinkman-Darcy-Forchheimer model.Comprehensive numerical solutions are obtained in the wide range of two main dimensionless parameters,i.e.the effective fluid-to-solid thermal conductivity ratio,0.001≤γ≤1.0,and the dimensionless volumetric heat transfer coefficient,1.0≤H≤1000.The effects of γ and H on the flow and heat transfer characteristics are analyzed.It is found that the local thermal non-equilibrium model should be adopted at the low values of γ and H for predicting the flow and heat transfer characteristics exactly.

Physical Model Test of Bank Protection Cross Section in Haiyang Nuclear Power Plant

MA Yuan-hua

2007, 28(4): 49-53,96.

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The physical model test is an essential link in the bank protection engineering design.It is the final verification to engineering design result,and afford the decision for the final plan of engineering design.This paper used the normal model test and the availability stress method to analyze the stability of Haiyang nuclear power bank protection project,and finally confirmed that the cross section design is safe and reason-able.

Finite Element Modal Analysis and Dynamic Experimental for Liquid Sloshing

LI Song, GAO Fang-qing, YANG Yi-ren, FAN Chen-guan

2007, 28(4): 54-57.

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In this paper the dynamic characteristics of liquid sloshing in a level column tank is studied by experimental analysis and numerical simulation method.Liquid system modes of different full rates under level power are simulated.We combine some specific experimental designs and the scan laser measure instrument,and find a better way to directly measure the liquid wave fluctuation.Ansys FEA software is used to simulate preferably low-rank modes and local modes of liquid systems,and dummy-mass method is used to correct the low-rank frequencies of liquid sloshing.The FEA numerical simulation results and the experimental results showed that mode analysis of the liquid systems can be solved preferably by combining the two methods.

Finite Element Analysis of Swelling Behaviors in Dispersion Fuel Plates

DING Shu-rong, HUO Yong-zhong

2007, 28(4): 58-62.

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Following the idea of micromechanics of particle reinforced composites,for the dispersion fuel plate,a representative element is chosen to study the thermal-mechanical coupled behaviors using the gradually increasing fission pressures which are corresponding to fission density and burnup,to simulate the mechanical contribution produced by particle fission to the Al matrix.The effects of the fission pressure,the thermal strain and the non-uniform distribution of the particles along the thickness on the swelling are investigated in details.Besides,the Mises stress distribution in the matrix is analyzed.The research results indicate that（1） the higher the particle volume fraction is,the quicker the velocity of particle swelling,（2） with the increasing of the fission pressures,the velocity of particle swelling increases sharply and the particles do not remain round,（3） on the conditions of normal work and for the chosen parameters,the effects of the thermal strain on the total deformation are not evident,（4） when the fission pressure is not big,the non-uniformity hardly affect particle swelling,however,with the increasing of fission pressure,the swelling of the non-uniformly distributed particles are distinctly higher than the uniformly distributed ones and this phenomenon is more and more evident,and（5） the stress distribution of the matrix is not spherical symmetry.

Study on Preparation of AUC by Means of Contrary Feeding

XU Kui, LIU Jin-hong, HU Bai-gui, LEI Mao-lin, CUI Chuan-jiang

2007, 28(4): 63-65.

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The precipitation of ammonium uranyl carbonate（AUC） use NH₃ and CO₂ gas by the contrary feeding method is investigated in this report.The influences factor such as reaction temperature,feed concentration,feeding speed has been studied.The experiment shows that controlling the reaction temperature in 60℃～70℃,feed concentration in 200g/L,feeding speed in 40L/h is feasible.The fluorine content of AUC crystal is under 1000μg/g,the bulk density of AUC is in 0.8 g/cm³～1.0g/cm³,and it has the excellent flow-ability.

Constitutive Modeling for Uniaxial Time-Dependent Ratcheting of SS304 Stainless Steel

KAN Qian-hua, KANG Guo-zheng, ZHANG Juan

2007, 28(4): 66-71.

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Based on the experimental results of uniaxial time-dependent ratcheting behavior of SS304 stainless steel at room temperature and 973K,a new time-dependent constitutive model was proposed.The model describes the time-dependent ratcheting by adding a static/thermal recovery into the Abdel-Karim-Ohno non-linear kinematic hardening rule.The capability of the model to describe the time-dependent ratcheting was discussed by comparing the simulations with the corresponding experimental results.It is shown that the revised unified viscoplastic model can simulate the time-dependent ratcheting reasonably both at room and high temperatures.

Study on Structure and Properties of Plasma Spraying Fe-Ni-B Coating

YANG Wen-feng, LIU Ying, YANG Lin, LI De-an, GAO Sheng-ji, TU Ming-jing

2007, 28(4): 72-75.

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Air plasma spray technique was used to prepare Fe-Ni-B coating on 1Cr18Ni9Ti stain steel substrate and the Fe-Ni-B coating was re-melted.The microstructure of Fe-Ni-B coating and interface con-figuration before remelting was analyzed using SEM and EDX apparatus.The micro hardness,thermal shocking performance,adhesion strength between coating and substrate was also studied.The results indicated that after the remelting,the coating microstructure became more compact,and diffusion and new ingredients appeared between the interfaces of coating and substrate,so the thermal shocking performance was improved.The adhesion strength between Fe-Ni-B coating and 1Cr18Ni9Ti stain steel substrate is 36.3MPa and micro hardness distributes at 470~570HV_0.2.The micro hardness of substrate near the coating is higher than that of the farside because of the thermal influence of spraying particles,however,the micro hardness of interface is relative low.

Recommendations on Legislative and Regulatory Framework and Regulatory Body of Nuclear Security in China

PU Ji-long, LI Xiao-yan

2007, 28(4): 76-80.

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This paper describes the definition of nuclear security that has been in changing from the cold war age to the post-911 period,and clarifies the close relationship and yet a clear distinction between nuclear security,nuclear safety and nuclear safeguard.Based on the analyses of the current state of nuclear security activities in China as well as the requirements and the law infrastructure,a legislative and regulatory framework of nuclear security and the mandate of a regulatory body in China are recommended.

Approach for Fault Diagnosis in Nuclear Power Plant Based on Rough Set and Decision Tree Theory

XU Jin-liang, ZHANG Da-fa, ZHANG Long-fei

2007, 28(4): 81-84.

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The new ID3 algorithm of leaning decision tree is proposed by combining the rough set and information entropy.The approach for fault diagnosis is proposed based on the new ID3 algorithm and rough set reduction algorithm,and is applied to the fault diagnosis in the nuclear power plant.The result shows that this approach efficiently differentiates the faults of the nuclear power plant,and can be applied in fault diagnosis domain for marine nuclear power plant.

Application of Improved BP Algorithm in Fault Diagnosis of Nuclear Power Equipment

XIE Chun-li, XIA Hong, LIU Yong-kuo, LIU Miao, ZHANG Bao-feng

2007, 28(4): 85-90.

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The error back propagation（BP） training algorithm for artificial neural networks was improved,by adjusting the coefficient of neuron according to the size of the training error,and an improved genetic algorithm used to improve the structure and weight of the traditional BP neural network simultaneously in this paper,which greatly increased the convergence rate of the training algorithm.The artificial neural network technology and the improved BP network training algorithm were applied to the nuclear power plant fault diagnosis.The fault of the break of the steam generator inverted U-tube in the nuclear power plant was taken as the example,and the fault diagnosis model was established.The simulation results showed that the application of this algorithm is feasible.

Safety Monitoring Modeling and Real Time Safety Analysis Based on Petri Nets

DONG Dou-dou, ZHOU Zhong-bao, ZHOU Jing-lun, ZHAO Zhao, FENG Jing

2007, 28(4): 91-96.

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In order to provide the efficient method for safety monitoring,this paper adopts the Petri nets to construct safety monitoring model and researches the qualitative and quantitative safety analysis based on Petri nets.The safety monitoring modeling based on Petri nest can effectively represent the system evolution from normal to danger;and especially can describe more than one danger event in one net.At last,the safety monitoring for nuclear reaction is illustrated to demonstrate the process of the constructing safety monitoring model and safety analysis.The method of safety monitoring modeling based on Petri nets is in accord with the human cognitive habits in descriptive way,and can reduce the complexity of modeling management for huge system.

Design and Experiment of Solenoidal Superconduct Magnet Applied to Sodium Electromagnetic Pump

YANG Zhi-da, HAN Wei-shi, WU Yu

2007, 28(4): 97-100.

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In this paper,solenoidal superconduct magnet which is applying to sodium electromagnetic pressure infuser,then the magnet center B reaches 4.66T when the quench current is 97 A.If reducing the excitation velocity,the center B can reach 5T,satisfying the need of sodium electromagnetic pump.pump is designed in detail and experimentally studied.The room temperature aperture length of this magnet is 600mm,the diameter is 160mm,and the magnetic induction intense in the center field（B） is 5T.The short superconduct thread sample is tested.The critical current is 464 A when the temperature is 4.2K and the B is 5 T,which is larger than the design current.The magnet is quenched training for ten times after reel and vacuum

Fatigue Experiment on Bursting Disk Device in Non-Active Heat Discharging System of Chinese Experimentation Fast Reactor

ZHOU Yi-hui, YOU Hong-xin, LI Yue

2007, 28(4): 101-103.

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Passive residual heat removal system is very important for faster reactors to ensure its safety.Bursting disk is one passive discharging device under over-pressure.Action performance of the bursting disk is carried out by adding fatigue loads repeatedly in this paper.The load stress is 80% of the nominal bursting pressure of the bursting disk,and the load cycles is over 10⁵.The experimental result shows that the action pressure difference before and after the fatigue experiment of the bursting disk is less than 1.5%,which indicates that the fatigue resistance of the bursting disk for the passive residual heat removal system is excellent,and it can ensure the reliable work of the passive system.

Numerical Simulation for Erosion-Corrosion Damage and Structure Optimization of High Pressure Air Cooler Tubes

DAI Zhen, SHEN Shi-ming

2007, 28(4): 104-107,127.

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For the leakage of high pressure air cooler tubes caused by corrosion,the effect of hydrody-erosion-corrosion,standard k-ε turbulence model and SIMPLEC method are adopted.The numerical results are in good agreement with the inspection of tube.Furthermore,the flow characteristics in tubes of different namic erosion on process of corrosion is analyzed by CFD simulation that is used to simulate actual flow in high pressure air cooler tubes of one corporation.For finding the exact position that was badly damaged by transition structures is studied,which would provide helpful reference for the improvement of air cooler tubes.

Simulator Training and Licensing Examination for Nuclear Power Station Operator

XU Ping-sheng

2007, 28(4): 108-111,121.

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For the recruitment,training and position qualification of the simulator instructors and feedback of training effect,the management approaches are formulated in "The System for Simulator Training and Licensing Examination of Daya Bay Nuclear Power Station Operators".The concrete requirements on the professional knowledge,work experience and foreign language ability of a simulator instructor are put for-ward.The process of instructor training is designed.The training items include the trainer training,pedagogy training,time management training,operation activities training during outage of unit,"shadow" training and on-the-job training on simulator courses.Job rotation is realized between simulator instructor and licensing personnel on site.New simulator instructor must pass the qualification identification.After a duration of 2 years,re-qualification has to be carried out.On the basis of the operator training method introduced from EDF（Electricite De France）,some new courses are developed and the improvement on the initial training,retrain-ing courses,the technical support and the experience feedback by using the simulator is done also.

Development of Multifunctional Radiation Monitoring Instrument Based on PLC Technology

LI Zi-qiang, ZHU Yu-ye, ZHUANG Min

2007, 28(4): 112-116.

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This eight-channel multifunctional Radiation Monitoring Instrument is developed by making use of the built-in high-speed counters and the powerful instruction system of the SIEMENS SIMATICS S7 translated between Graduation Apparatus method and Formula method.The logicality of the high-dosage warning system is processed itself.The signal output will drive the alarm lights and bell directly.This paper series Programmable Logic Controllers（PLC） to record and process the pulse signal output by the detectors.The instrument with functions,such as analog and digital display,digital storage of digital data,pulse signal generator,network communication,can connect various types of pulse detectors.The initial process can be mainly describes the configuration,programming and feature of the instrument.

Study of Method to Determine Boron Isotope Abundance Using Mass Spectrometry

DENG Hui, XU Chuan, ZHANG Ge

2007, 28(4): 117-121.

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This paper introduced the measurement of natural boron isotope abundance ratio detecting of BO²―by mass spectrometry.The uncertainty of measurement result was cut down by the work of selecting emit reagent,deducting the contribution of oxygenium and adjusting the mass fractionation effect.

Research of Method for Activity Measurement of Neutron-Activation-Foil

GU Zhen-jun, ZHANG Yi-yun, XU Xian-qi

2007, 28(4): 122-124.

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This paper puts forward a new method measuring the activity of neutron-activation-foil using 4πβ-γ coincidence equipment without making thin film source.By changing the voltage of photomultiplier tube,keeping the same efficiency of the γ detector in detection of γ photon and X ray of K shell,we can obtain the activity of neutron-activation-foil,without using efficiency extrapolation method.Theory analysis indicates that the method is feasible.

Application and Prospect of High-Speed Digital Camera in Control Rod Drive Line Characteristic Experiment

HE Jun-shan, JIANG Xian-guo, HUANG Zhao-qing, HU Jun, ZHAO Hua

2007, 28(4): 125-127.

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The High-Speed Digital Camera experimental technique for obtaining the displacement,velocity,acceleration and the most biggest rebound height of the Control Rod Drive Line（or CRDL） in the CRDL characteristic experiment are introduced,and the prospect of this application is advised too.

2007 Vol. 28, No. 4