核动力工程

Thermal-Hydraulic Analysis and Pulsed Characteristic Analysis for Xi’an Pulsed Reactor

CHEN Li-xin, ZHAO Zhu-min, YUAN Jian-xin

2006, 27(6): 1-4,17.

Abstract(10) PDF(0)

Abstract:
This paper calculates the thermal-hydraulic parameters of the reactor core in steady ar-rangement and the pulsed parameters of the pulsed core with the computer program PRTHA,PULSE and TEMPUL.The calculation result shows that the heat transfer of XAPR is safe.Calculation in this paper can be an reference for the safety analysis of XAPR.

Research on Power Effect of Th-U Fuel on TACR （Thorium Based Advanced CANDU Reactor）

WANG Yong-gang, SHEN Shi-fei, WANG Kan, SHI Gong

2006, 27(6): 5-8.

Abstract(9) PDF(0)

Abstract:
Researching on the CANDU lattice physics,average power of the core is carried out.Though the value of power may have effect on the nuclear reaction in the TACR core that used thorium fuel, the lattice cross sections are also different in various power conditions.This paper has studied the evolution of the lattice cross section data of the all uranium fuel lattice and the Th-U lattice with the radiation value.The ²³³Pa and ²³³U weight content in the thorium fuel in different power conditions is also examined.The results show that the power has effect on the macro section of the thorium fuel.When doing the core calculation with thorium fuel,the history-based local-parameters methodology is adopted.

Design and Application of Reactor Core with Tight-Lattice Rod Type Fuel Element

DONG Xiu-chen, XU Chuan, LIU Ju-kui

2006, 27(6): 9-12.

Abstract(6) PDF(0)

Abstract:
This paper preliminarily analyzed the advantage of a reactor core with rod type element in tight triangle lattice,and briefly introduced its application in small and medium nuclear power plants.The analyzing and comparison indicated the great prospect of the tight lattice.

Thermal Stratification Study for Pressurizer Surge Line

ZHANG Yi-xiong, YANG Yu

2006, 27(6): 13-17.

Abstract(7) PDF(0)

Abstract:
In order to confirm the structural integrity of pressurizer surge line affected by thermal strati-fication,this paper theoretically analyzes the criterion of thermal stratified occurrence,establishes the thermal stratified transient by start-up of reactor,and studies the calculation method of thermal stratified stress.A complex 3-dimension problem is simplified into a combined one of 1-dimension and 2-dimension.Consider-ing ANSYS code function,an engineering method is put forward for thermal stratified stress calculation of pressurizer surge line.

Experiment of Effect of Dissymmetry Throttling and Heating on Oscillation between Double Parallel Channels

HUANG Jun, HUANG Yan-ping, WANG Fei, LU Dong-hua, LI Hong-bo

2006, 27(6): 18-22.

Abstract(10) PDF(0)

Abstract:
The research of dissymmetric parameters are very useful to understand and eliminate the in-stability in parallel channels,and improve the stability of system.The experiment has been done in the ther-mohydraulics loop by double parallel round channels.With the inlet throttling or the degree of dissymmetry throttling increasing,the critical heating power of oscillation is increased,but the period of oscillation is not cillation is not affected,and the amplitude of oscillation is increased.The stability boundary of oscillation in double parallel channels has been finished,and the experimental correlation is obtained.affected,and nonlinear effects of amplitude of oscillation are observed experimentally.With the dissymmetry degree of heated power increasing,the critical heating power of oscillation is reduced,but the period of os-

Design of Super-Fluid Helium Cooling Cycle and Optimization of Operating Temperature of 1.3 GHz SRF Cavity Systems for PKU-SCAF

DU Hong-peng, WANG Li, CHEN An-bin

2006, 27(6): 27-32.

Abstract(12) PDF(0)

Abstract:
Due to the exponential dependence of the BCS surface resistance with temperature,reducing the operating temperature of SRF cavity will result in lower radio-frequency loss for the cavity,but the effi-ciency of the cryogenic plant reduces drastically too.In this paper,the saturated super-fluid helium cooling cycles and operation temperature for a 1.3GHz superconducting resonance frequency cavity system were analyzed in terms of improving the refrigeration efficiency of SRF cooling system and lowering the cavity dynamic loss.The optimized operation temperature for the 1.3GHz SRF cavity is around 1.95K.The suitable cooling cycle is proposed finally.

Numerical Simulations on a High-Temperature Particle Moving in Coolant

LI Xiao-yan, SHANG Zhi, XU Ji-yun

2006, 27(6): 33-37,55.

Abstract(9) PDF(0)

Abstract:
This study considers the coupling effect between film boiling heat transfer and evaporation drag around a hot-particle in cold liquid.Taking momentum and energy equations of the vapor film into ac-count,a transient single particle model under FCI conditions has been established.The numerical simulations on a high-temperature particle moving in coolant have been performed using Gear algorithm.Adaptive dy-namic boundary method is adopted during simulating to matching the dynamic boundary that is caused by vapor film changing.Based on the method presented above,the transient process of high-temperature particles moving in coolant can be simulated.The experimental results prove the validity of the HPMC model.

Application of Visual Modelization Technology to Reactor Thermohydraulics Analysis Programmes

XU Zhen, YANG Yan-hua, LIN Meng, YANG Xiao

2006, 27(6): 38-41,51.

Abstract(9) PDF(0)

Abstract:
Visual modelizaton and XML was used to build a thermo-hydraulics security analysis model library for RELAP5 programme.The modeling system frame was constructed by the components transferred from this model library.Interfaces were described with thermo-hydraulics parameters based on windows platform.Every component was linked with the corresponding interface and input parameters,and RELAP data deck was created after checking errors.The analysis of a simple fluid flow in pipe verified that this technology could simplify the use of RELAP and improve the efficiency of study.

FRS Analysis for Pumping Station Structure of NPP Considering SSI Effect

LIANG Wan-shun, LÜ Fei, ZHANG Chao-qi

2006, 27(6): 42-46.

Abstract(9) PDF(0)

Abstract:
In this paper,a dynamic analysis for pumping station structure of NPP is carried out using Super SAP and CLASSI program under the condition of ultimate safety ground motion and operation safety ground motion.The series of seismic response were transformed by FFT（Fast Fourier Transform） after the time-history analysis and in turn the Floor Response Spectra（FRS） of structure is achieved.The calculation results under the two conditions are compared in detail.Based on the comparison made between the two results（considering SSI and fixed base） under-mentionedi,t indicates that this method and program is practical.It also clearly shows there are significant effects of SSI on the FRS peak value,FRS shape and the response spectrum value in the high frequency domain.

Welding Defect Extraction of X-Ray Image Based on Adaptive Morphological Filtering Operator

LUO Ai-min, YIN Guo-fu, WEI Wan-ying

2006, 27(6): 47-51.

Abstract(9) PDF(0)

Abstract:
When mathematic morphological filtering methods are applied on the welding defect extraction of X-ray image, the key is the size of structural elements. An adaptive morphological filtering is proposed in this paper:Firstly the sizeof structural elements is chosen on the basis of the result of watershed transformation on scanning beams which is vertical to the welding image, and the size can be adaptively adjusted according to the size of the welding defect. Then the mathematic morphological opening operator is applied on the image to subtract the result from the original image, and the filtering results are reached finally. This method was applied in the extraction of welding defect edge to obtain satisfactory results.

Finite Element Analysis of Plastic Limit Pressure of Elbows with Local Thinned Area on Inner Wall of Extrados

DUAN Zhi-xiang, SHEN Shi-ming

2006, 27(6): 52-55.

Abstract(11) PDF(0)

Abstract:
The paper discusses the plastic limit pressure of elbows with local thinned area on inner wall of extrados. In this research, finite element analysis (FEA) has been used. The results of FEA show that the plastic limit pressure of the elbow with local thinned area on inner wall of extrados are slightly lower than the one of the corresponding elbow with local thinned area on outer wall of extrados. By data fitting of FEA, an empirical formula of the limit pressure for elbows with local thinned area on inner wall of extrados has been attained.

Evolutionary Morphology of Short Fatigue Cracks of 1Cr18Ni9Ti Weld Metal

ZHAO Yong-xiang, YANG Bing, GAO Qing

2006, 27(6): 56-61,86.

Abstract(8) PDF(0)

Abstract:
Evolutionary morphologies of the short crack propagation of 1Cr18Ni9Ti weld metal are investigated on specimen surface and in depth direction.To be agreement with the previously effective short fatigue crack（ESFC） criterion,attention is paid to the formation zone of the dominant ESFC（DESFC）,which results in the specimen failure,in the micro-structural short crack（MSC） regime and then the tip zone（s） ahead of the DESFC in the physical short crack（PSC） regime.Results show that the ESFCs imitated from the bounds between the ferrites and the austenite matrix.The ferrites are distributed randomly in an angle range less than 45 degree to the cross-section perpendicular to the loading axle.The initiated ESFCs on surface propagate to be inclined to the direction perpendicular to the loading axle due to the stronger microstructural constraints.In the depth direction,the initiated ESFCs grew perpendicular to the loading axle first and then to be inclined to the direction perpendicular to the material columnar grain structure formation.When the sizes of some longer ESFCs,with closer tips ahead the growth paths and similar directions,get the material maximum barrier size,coalescence may occur to form at a true DESFC.In the PSC regime the formed DESFC grows to be more and more inclined to the direction perpendicular to the loading axle on the surface.But in the depth direction,it grows to the direction perpendicular to the formation direction of the material columnar grain structure first and then to be inclined to the direction with 45 degree angle to loading axle.Finally,the specimens are fractured mostly in direction perpendicular to the loading axle.It revealed that there is significant difference between the evolutionary morphologies of long and short fatigue cracks.

X-Ray Photoelectron Spectroscopy Analysis of Film Formed by Reaction CO₂ and Zirconium Hydride

ZHAO Ping, PENG Qian, KONG Xiang-gong, ZOU Cong-pei

2006, 27(6): 62-65,69.

Abstract(9) PDF(0)

Abstract:
The chemical states of carbon,oxygen and zirconium at the depth of 100nm,200nm and 300nm in a film created by reaction of CO₂ with zirconium hydride upon the zirconium hydride sample had been investigated with the X-ray Photoelectron Spectroscopy before and after heating to 700℃,and the X-ray Photoelectron Spectroscopy analysis results had been calculated using the relative sensitivity factor method.The results showed that the film consisted of carbon,oxygen and zirconium,and also —OH bond and C—H bond before heating to 700℃,after heating to 700℃ there were not only —OH bond and C—H bond but also —COOH in the hydrogen permeation barrier,and the quantity of carbon and oxygen which were com-bined with hydrogen has increased.

Application of Initiating Condition and Emergency Action Level in NPP at ATWS

ZHANG Chun-ming, XU Chuan

2006, 27(6): 66-69.

Abstract(11) PDF(0)

Abstract:
The report introduces the application of Initiating Condition and Emergency Action Level in NPP at ATWS,and compares the difference of Emergency Action Level for same Initiation Condition at ATWS between PWR and CANDU NPP

Discussion about Design Basis Flood of Site of Research Reactors by River

RONG Feng, ZHAO Jian-jun, DU Qiao-min, ZHANG Ling-yan

2006, 27(6): 70-73.

Abstract(9) PDF(0)

Abstract:
This paper presents the well-defined standard in relation to design the basis flood of the sites of research reactors by river.It is based on the concept of some relational standards,analysis of hydrological calculation technology and methods,and analysis of accident dangerous degrees of research reactor,as well as in combination with the engineering practices.The flood preventing standard for research reactors with higher power should be the same with that of the nuclear power plants.

Simple Probabilistic Method for Relative Risk Evaluation of Nuclear Terrorism Events

ZHANG Song-bo, TIAN Dong-feng, WU Jun

2006, 27(6): 74-81.

Abstract(7) PDF(0)

Abstract:
On the basis of the event-tree and probability analysis methods, a probabilistic method of nuclear terrorism risk was built, and the risk of terrorism events was analyzed. With the statistical data for and hypothetical data for relative events, the relative probabilities of the four kinds of nuclear terrorism events were obtained, as well as the relative risks of these four kinds of nuclear terrorism events were calculated by using this probabilistic method. The illustrated case show that the descending sequence of damages from the four kinds of nuclear terrorism events for single event is as following: nuclear explosive and improvised nuclear explosive, nuclear facility attacked, and “dirty bomb”. Under the hypothetical condition, the descending sequence of possibilities for the four kinds of nuclear terrorism events is as following: “dirty bomb”, nuclear facility attacked, improvised nuclear explosive and nuclear explosive, but the descending sequence of risks is as following: “dirty bomb”, improvised nuclear explosive, nuclear facility attacked, and nuclear explosive.

Rough Set Theory and Its Application in Fault Diagnosis in Nuclear Power Plant

CHEN Zhi-hui, XIA Hong, HUANG Wei

2006, 27(6): 82-86.

Abstract(9) PDF(0)

Abstract:
Rough Set theory is the mathematic theory that can express and deal with vague and uncertain data.There is complicated and uncertain data in the fault feature of Nuclear Power Plant,so that Rough Set theory can be introduced to analyze and process the historical data to find out the rule of fault diagnosis of Nuclear Power Plant.This paper introduces the Rough Set theory and Knowledge Acquisition briefly,and describes the reduction algorithm based on discernibility matrix and its application in the fault diagnosis to generate rules of diagnosis.Using these rules,three kinds of model faults have been diagnosed correctly.The conclusion can be drawn that this method can reduce the redundancy of the fault feature,simplify and optimize the rule of diagnosis.

State Commissioning of Gas Stripper Unit of Boron Recycling System of Ling’ao Nuclear Power Plant

LI Kai-feng, LUO Ming-kun, LI Shu-zhou, ZHANG Wen-li

2006, 27(6): 87-90.

Abstract(12) PDF(0)

Abstract:
This paper describes the function and states of the gas stripper unit of boron recycling system of Ling’ao Nuclear Power Plant.Based on the states commissioning of the gas stripper unit of boron recycling system,this paper gives out the itmes in the states commissioning of gas stripper unit and parts of the state parameter curves of the gas stripper unit from starting-up to stopping according to the normal sequence.It aims at the problems appearing during states commissioning,analyzes the reason,and proposes the measures to handle the problems.The result indicates that states operation of gas stripper unit of boron recycling system fully satisfy the system design requirement.

Research and Design of China Intehral Reactor Plant Innovative Containment

QIN Zhong

2006, 27(6): 91-93,98.

Abstract(7) PDF(0)

Abstract:
China Integral Reactor Plant（CIP） is a light water cooled,300MWe power reactor under development by Chinese National Key Laboratory of Reactor System Design Technology.CIP features an integral reactor vessel that contains the CRDM and all the major reactor coolant system components including the reactor core,the coolant pumps,the once-through steam generators and the pressurizer.This integral design approach eliminates the large coolant piping and large LOCAs,and thus provides with higher level of securities.This paper introduces the selection of the CIP containment system,the design of containment,the determination of the design pressure for the containment and the calculation analysis of the containment structure.

Precise Orientation Technique for Auto-Control of Cranes for Nuclear Waste Storehouse

YANG Zhi-da, LIU Shao-you, QI Xue-feng, HAN Wei-shi

2006, 27(6): 94-98.

Abstract(9) PDF(0)

Abstract:
11UKT in Tian Wan nuclear power station is the temporal storehouse of radioactive solidification waste.When operator directly operates the crane to load in the storehouse,the operator will be subjected to nuclear radiation,with intensive workload and poor orientation precision.In this paper,the crane for the storehouse of radioactive solidification waste 11UKT is improved technically,based on the laser measurement instrument,variable frequency speed regulation technology and PLC.After the improvement,the orientation precision of the crane is up to ±2mm.Operation is computerized,and the operator can complete the orientation by hitting the mouse.It may reduce the workload of operators,and thus avoid excessive nuclear radiation to the operators.

Relay Aging and Reliability Analysis of Nuclear Power Station

ZHAO Xi, HUANG Wei-gang, CHEN Shi-jun, ZHANG Xiao-ming, LI Shao-ping

2006, 27(6): 99-102.

Abstract(10) PDF(0)

Abstract:
Based on the analysis and test of the aging failure and reliability of LEACH relays produced in 1999,it was realized that the failure is due to the resistance decrement and heat generation caused by insu-lation material degradation.Measuring the outer shell temperature can monitor the aging process.For the unreliable batch,it is necessary to start the batch replacement program.

Study on Design of High Pressure Ionization Chamber

LIU Chun-yu, HAN Wei-shi, LI Jian-ping, REN Yi-chang, LIU Shu-dong, WAN Guo-qing

2006, 27(6): 103-105,112.

Abstract(9) PDF(0)

Abstract:
This paper introduces the design of a High Pressure Argon Ionization Chamber.The choosing of the working gas and the material for the chamber is based on the calculation results of the MCNP program and the EGSnrc program.Fit parameters are gained by analyzing the effect of various factors,such as thick-ness of the wall,diameter of the wall,and the pressure of the working gas,on the performance of the ioniza-tion chamber.The experimental results show that the energy response of the ionization chamber is fairly well.

Electrochemical Behavior of T225NG Titanium Alloy in High Temperature and High Pressure Aqueous Solution

WEN Ju-hua, LAI Xu-ping

2006, 27(6): 106-108.

Abstract(11) PDF(0)

Abstract:
The polarization curves of T225NG Titanium Alloy in high temperature and high pressure aqueous solution with different concentrations of chlorine ion and dissolved oxygen have been measured by electrochemical method, and its electrochemical behavior and corrosion mechanism have been analyzed. The active regions of the anodic polarization curves of T225NG Titanium Alloy have not been found in the test condition. Passive current density and corrosion of T225NG Titanium Alloy increases when the concentration Cl^- and dissolved O₂ becomes high. There is a formation of oxide film i.e. A region in the solution which Cl^- is below 0.005mg/L while there are formation of oxide film and release of Cl₂, i.e. A and B regions in the solution which Cl^- is above 0.02mg/L for the polarization curves of T225NG Titanium Alloy.

Preliminary Radiological Consequence Assessment of China Pilot HTR Power Plant

QU Jing-yuan, CAO Jian-zhu, LI Hong, LIU Yuan-zhong, FANG Dong

2006, 27(6): 109-112.

Abstract(10) PDF(0)

Abstract:
This paper presents the major results of a preliminary assessment on the radiological impact of China pilot HTR power plant. They include the calculation of inventory of radio-nuclides in the reactor core, release of radioactivity into the atmosphere during routine operation, source term of release and the resulting radiation dose in the event of an accident. The results of this assesment have shown that the radiation dose received by the general public as a result of radioactivity release under normal operation conditions will be far below the dose limit defined in national regulations. The potential exposure to the population in the event of design basis accidents will be significantly lower than the generic intervention levels for taking sheltering.

Theoretical Model Study of Radioisotope Microbattery Based on β-Radio-Voltaic Effect

CHU Jin-kui, PO Xiang-hao, WU Hong-chao

2006, 27(6): 113-118.

Abstract(14) PDF(0)

Abstract:
As the developing of MEMS（micro electromechanical system）,micropower becomes a very key problem in MEMS application gradually.The paper accounts simultaneously for the choice and decay type of isotope,particle energy spectrum,the energy loss rate of emitted particle in the mass,semiconductor characteristic and generation and recombination of carriers and sets up a theoretical model of radioisotope microbattery based on β-radio-voltaic effect.The model can calculate short circuit current and open circuit voltage of microbattery.The simulated result is slightly bigger than literature results;doped density of diffu-sion layer,the diffusion depth and radiation particle activity respectively influences export parameters of bat-tery.The model is considerably instructional and useful for developing microbattery.

2006 Vol. 27, No. 6