摘要:The ASME code and RCC-M code are widely used in the design and manufacture of class 1 nuclear power equipment. In general,both of them are used simultaneously in the fabricating of primary device by manufacturer. Welding is the most critical and important process of the nuclear power equipment manufacturing. In this paper,the comparison of the class 1 nuclear component welding in ASME code and RCC-M code is introduced by respect of standard structure,requirement,welding temperature,heat treatment and the weld test coupons. The difference of standard application is analyzed from the perspective of users,which lays a foundation for formulating reasonable welding process.
摘要:The prefabrication of BOSS requires multi-layer multi-pass welding with three-dimensional saddle shaped trajectories,which makes robot teaching and playback technology not suitable for actual use demands. Therefore an offline programming technology is developed, which allows users to self-define the arrangement of beads. By inputting the number of layers,the number of beads in every layer and the sectional area of single pass,all the welding trajectories can be generated automatically. Welding experiments indicate that this technology is suitable for BOSS prefabrication,which can greatly improve the welding quality and productivity.
关键词:prefabrication of BOSS;three-dimensional saddle shaped trajectory;offline programming technology
摘要:As one of the most important nuclear power standards,mechanical component standard of nuclear island is an important safeguard for nuclear power construction. At present,the coexistence of the two sets of mechanical component standards has brought unnecessary duplication and waste to the design and manufacture of mechanical components of nuclear islands. Among them,the differences between the two sets of welding material standards,the causes of the differences and the main difficulties in solving the differences are analyzed,and the solutions are given. Finally, the current work progress is introduced. The pioneering work on technical route unification of welding material standards has great practical significance for improving the standard system of nuclear power in China, promoting independence of the standard and facilitating the "go global" of China’s nuclear power.
关键词:mechanical components of nuclear islands;welding material standards;technical route unification
WANG Zhong,XIAO Jingbin,HU Xiaogang,TANG Yangyang,CHANG Hongpo,ZHU Zhiyi
Vol. 49, Issue 4, Pages: 15-25(2019)
摘要:According to the present status and features of key components for nuclear power,such as piping prefabrication,valves to take over the butt welding,control rod drive mechanism Ω seal welding,electric heating element tube replacement in service,neptunium tank sealing welding and radioactive source assembly welding,put forward the solution for automatic welding of intelligence. With innovative thinking,new technology,new equipment to replace the traditional manual welding,improve product quality,reduce labor intensity. Part of the auto welding equipment also replaced the imported welding equipment,to upgrade the localization rate of the nuclear power to welding equipment,to help promote the competitiveness of the internationalization of nuclear power.
关键词:HPR1000;piping prefabrication;narrow groove hot wire TIG welding;Ω seal welding;replacement in service
摘要:Based on the groove type and dimension of pipeline BOSS weld in nuclear power plant,and the non-destructive testing scheme of BOSS weld in manufacturing and installation stage,the main causes of defects types and weld failures are analyzed. Taking the BOSS weld of main pipeline as an example,aiming at the main characteristics of weld structure and dimension,the key points of radiographic technology,film sensitivity and limitation of BOSS weld are studied and verified,which provides reference for the radiographic detection scheme of pipeline BOSS weld in nuclear power plant.
摘要:Ni-based welding material has a widely application in the fabrication of the key components in nuclear power plants. Two types of welding defects,ductility-dip crack and point-like defect,in the Ni-based weld metals are investigated. Based on the calculation results by Thermo-calc with TTNi8 database,several welding wires containing different Nb and Mo contents are designed and fabricated. The results show that the room temperature strength and plasticity of the weld metals improve as the Nb or Mo content increases,which effectively reduce the ductility-dip cracks and point-like defects. Finally,Ni-based welding wire with high welding defects resistant is obtained,which can meet the use requirements for nuclear power plants.
摘要:In order to evaluate the high cycle fatigue performance of laser weld joint with filler wire,the 2 ×106 high cycle fatigue strength of 0.7 mm thick laser weld joint with filler wire is evaluated by up and down method. SEM is used to analysis the fracture surface and fracture position. The results showed that the fatigue strength was 396.6 MPa. The fracture surface showed no precipitated phase. The crack source zone showed cleavage features,which mean the crack prolonged along the grain boundaries at early stage. The crack developing zone showed fatigue striations which became sparse with crack prolonging. Fracture zone feature was same with the tensile fracture surface which showed dimples and micro-holes features. The crack was originated from weld toe region on the top surface and prolonged along the thickness direction. During the propagation along the weld direction,the crack spread across the fusion line and in the weld zone and the adjacent base metal zone.
关键词:laser welding;up and down method;Hastelloy C-276;fatigue strength
摘要:The toughness of NiCrMoV steel welded joints for nuclear power low-pressure welded rotor is investigated. The impact toughness tests are carried out about the base material,joint heat affected zone,columnar crystal zone in weld,and the fine grain zone in weld. Combining with the fracture morphology and microstructure characteristics,the interrelationship mechanism between resilience and organization is studied. The results show that the impact property of each zone in welded joints can meet the requirement,but the impact property of the heat-affected zone fluctuates greatly. The cracking of the columnar crystal zone along the grain boundary makes the impact property weak. The cracks extend along the columnar grain boundary and a small amount of carbide precipitate on the columnar grain boundary,which is the main reason for the low toughness of the columnar crystal region in the weld.
摘要:HPR1000 steam generator is the third generationa nuclear power technology which be developed independently by China.This paper introduces the structural characteristics of HPR1000 steam generator,and describes the welding materials and process requirements for its key parts. Meanwhile,the key welding processes to be implemented,such as the stainless steel cladding weld of primary head,tube sheet cladding weld,tube-to-tube sheet weld,primary nozzle safe end weld,have been introduced in detail. It lays a foundation for the mass production of subsequent HPR1000 steam generator and provides a powerful technical guarantee.
SUN Fucheng,WANG Weibo,ZHANG Zhiqiang,WANG Lan,WU Yidang
Vol. 49, Issue 4, Pages: 54-58(2019)
摘要:The application of narrow gap hot wire TIG welding for welds in CPR1000 reactor pressure vessel import and export nozzle and the nozzle safe-end is summarized. Aiming at the unqualified problem of radiographic inspection of welds,the main causes of failure are found from the precision control of the positioner assembly,welding operation,atmosphere protection and control and other aspects. The welding process is improved from the close welding operation,weld clearance,environmental and other aspects. Through above measures,the welding quality and the primary qualification rate of radiographic inspection of weld are sharply improved,which provides valuable experience for the practical application of narrow gap TIG welding technology in domestic nuclear island main equipment.
摘要:According to the welding of the main circuit pipelines of nuclear power plants such as M310,CPR1000 and AP1000 in China,automatic welding technology has been successively implemented,which has significant effects in improving construction efficiency and quality. Combined with the characteristics of Russian VVER stacked main pipeline composite steel material,the present situation of automatic welding of main pipeline of nuclear island in China is fully discussed. It is of great significance to develop the construction technology of composite steel automatic welding for main pipeline with Chinese characteristics, utilize foreign resources and promote the feasibility study of international cooperation.
关键词:composite steel main pipe;argon arc with narrow gap;automatic welding technique;application;feasibility research
摘要:The 16MND5 RPV steel by electrical additive manufacturing was aged at 450 ℃ for 3 000 h. The effect of aging time on mechanical properties and structure was analyzed by mechanical properties test and microstructure observation. The experimental results show that with the extension of aging time,the tensile strength and yield strength of the specimens were increased by 5 MPa and 6 MPa,respectively,and the elongation and fracture shrinkage after the fracture remained unchanged. The stable crack propagation energy Wp1 of the sample decreases,resulting in a decrease in crack propagation energy Wp,resulting in a decrease in total impact energy Wt of 47 J. The microstructure is still pro-eutectoid ferrite and granular bainite before and after long-term thermal aging.
摘要:Neutron diffraction provides a unique scientific guarantee for accurate measurement,analysis and characterization of material properties such as structure,micro-defects and residual stresses of engineering materials,which is an ideal tool for in-depth study of material characterization and life assessment mechanism. This paper outlines the basic principle of neutron diffraction measurement,reviews the application of neutron diffraction technology in the fields of welding stress engineering and life extension technology of nuclear power structure,auxiliary optimization of welding heat treatment process,etc.. Finally,according to the characteristics of neutron diffraction engineering spectrometer,the future prospects of this technology in the field of material research are prospected.
摘要:The measurement of δ ferrite contention in the weld of austenitic stainless steel is a key step of the welding procedure qualification and the acceptance of welding materials and welding certificate. There are controversial and confused points in RCC-M standard about the measurement of δ ferrite contention in the weld of austenitic stainless steel. Put forward some cognition and understanding about the controversial and confused points in RCC-M standard and discuss a series of problems of the measurement of δferrite contention in the weld of austenitic stainless steel combined with the practical engineering experience and formation mechanism of ferrite in weld. The relevant controversial items concerning the determination of δ ferrite content in austenitic stainless steel welds in S section of RCC-M are clarified.
摘要:The pressurizer immersion heater,as one of the important components of the pressurizer in PWR nuclear power plant,is directly immersed in the coolant with the high temperature, high pressure and high nuclear radiation in the primary circuit. As the pressure boundary to bear the external pressure of the primary circuit,the quality of the weld between the sheath and end plug is required very strictly and the structure is very special. By studying the weld structure and welding technology,a kind of welding procedure which not only meets the requirement of high quality,but also can be applied in engineering is given.
关键词:nuclear power plant;pressurizer;heater;welding procedure
摘要:Some BOSS welds in nuclear power plant are found to contain many defects,such as incomplete fusion,slag,porosity and so on. Causes of BOSS weld defects are investigated and analyzed to be lack of experience for welders,improper implementation and control of the welding process,etc. Based on the conditions of defects and sites,some types of potential solutions(including localized repair,replacement of new pipes or BOSS,Overlay welding,evaluation & monitoring) are put forward to deal with the BOSS weld defects in various situations. Based on the experience,the optimum suggestions of groove angle,welding process and non-destructive inspection of BOSS weld are put forward,to reduce the probability of BOSS weld defects and enhance the safety and economy of the nuclear power plants.
YANG Licai,QIU Tian,ZHANG Yabin,CHEN Haibo,WANG Xuxin,WU Hao,TANG Yuan
Vol. 49, Issue 4, Pages: 91-101(2019)
摘要:A mockup-to-production method was proposed to simulate the residual stress in multi-pass welding of large structures.Firstly,the mockup was manufactured and tested to obtain data such as temperature cycle and residual stress. Then,the numerical calculation of the residual stress of the mockup was carried out. The model and algorithm of the mockup were calibrated by the test data,and a series of optimization and efficient calculation were carried out,such as the simplification of the weld path. Finally,the optimization algorithm and model were used to simulate the residual stress of large components. The residual stress in the nuclear reactor pressure vessel(RPV) head with two J-type welds at the locations of non-center hole were efficiently simulated with the proposed method,in addition,the superposition effect at the region between the two J-type welds were investigated. Results show that the mockup-to-production method is an efficient and effective method for the simulation of large nuclear welded structures,the superposition effect at the region between two J-type welds in RPV head is not significant.
摘要:The selection principle and engineering application of duplex stainless steel welding consumables were reviewed. The results show that the principle of "quasi-component matching" can be adopted in the selection of welding consumables for this steel,that is,to make the content of Cr in the weld as close as possible to the base metal,to increase the content of Ni and to add an appropriate amount of N,to reasonably control the ratio of ferrite to austenite in the weld,and to ensure the satisfactory corrosion resistance and weldability of the joint. There are five types of steel welding consumables,and various Processes have their own characteristics. The combination processes of FCAW backing welding and various high efficiency welding methods have obvious advantages. The duplex stainless steel welded joints with different thicknesses or positions,using matched welding consumables and reasonable processes,have been successfully applied in different projects. The quality stability of the flux-cored wire still needs to be strictly controlled.
摘要:This paper briefly introduces the principle of near net shape forming and technical characteristics of electrical additive manufacturing(EAM). A preliminary study on the properties and characteristics of EAM08CrMo that is manufactured by EAM is carried out,which provides technological support for the application of EAM. By testing and analyzing the chemical composition,micro-structure and macro-mechanical properties of EAM08CrMo,it is verified that the properties of material manufactured by EAM,the macro-properties are well-distributed,without thickness effect and directionality. By testing and analyzing the changes of micro-structure and macro-mechanical properties of EAM08CrMo before and after thermal aging treatment,it is concluded that the effect of thermal aging treatment on microstructure and impact toughness is little,but the strength has a slightly decrease.
摘要:Microstructure and segregation behavior during solidification in GTAW deposited metal of new type nickel alloy welding wire are investigated by OM,SEM and EDS. The results show that both metallographic structure of deposited metal of welding wire 1# and 2# is similar columnar crystal with interdendritic segregation zone, but no Laves+γ eutectic structure exists in 2# deposited metal.The partition coefficients of Nb,Ta,Mo at the beginning of solidification are less than 1,which incline to distribute in residual liquid phase during crystallizing. The partition coefficients of Fe at the beginning of solidification is over 1,which inclines to distribute in solid phase. Ni and Cr tend to evenly distribute between liquid and solid phase. Adding Ta in welding wire 2# has no obvious influence on partition coefficients of other elements,while has significant effect on microstructure,which avoids the formation of low melting point Laves+γ eutectic structure and then shortens the crystallizing temperature interval.
关键词:nuclear power;nickel base alloy;welding wire;tantalum
摘要:This paper introduces the typical defects and causes of the sealing lip weld for nuclear-grade stainless steel valve,analyzes the failure of important repair processes that affect the welding quality. It has developed the key technical points of the repair and quality control for the valve sealing lip weld,including sealing lip weld cutting,mating surface grinding,component cleaning and inspection,valve body cap assembly,welding and post-weld inspection etc. It also proposed the follow-up improvement direction of the repair for the valve sealing lip weld on the nuclear power site.
摘要:Laser butt welding of guide sheath of pressurized water reactor control rod guide tube(CRGT) is studied. The laser welding heat source,laser welds shrinkage of guide sheath and laser welding deformation are modeled and analyzed. The simulation technology of laser welding deformation of guide sheath is established,which provides theoretical guidance for the manufacture of laser welding of CRGT,including laser welding test and thermal cycle test,macroscopic appearance of weld,residual stress test,heat source model establishment and parameter determination,laser weld shrinkage model and welding deformation prediction. Finally,the stable laser welding parameters are obtained,should be tested using a φ10.26 mm drop bar gauge can go though the CRGT freely in four positions of 0°,90°,180°,270° with the speed of 4~5 m/min,and the friction force is less than 9.07 kg.
关键词:control rod guide tube;guide sheath;laser welding;numerical simulation;stainless steel
MA Shuli,LUO Ying,WANG Xuxin,ZHOU Gaobin,ZHANG Yabin,QIU Tian
Vol. 49, Issue 4, Pages: 133-137(2019)
摘要:The safe-end weld of reactor pressure vessel nozzle is dissimilar metal weld,which connects low alloy steel and stainless steel with Inconel 690. The welding material Inconel 690 is easy to generate micro-cracks,lack of fusion,oxide inclusions and other defects in the manufacturing process. By analyzing defect generation mechanism and combining actual manufacturing situation,the effects of chemical composition,welding method,welding parameters,auxiliary procedure measures and groove structure on the defect sensitivity of welding material Inconel 690 are studied. The results show that reasonable control of alloy element content can reduce the sensitivity of crystal crack. Appropriate reduction of welding heat input and avoidance of molten pool overheating can reduce the sensitivity of crack and lack of fusion. Control of groove shrinkage deformation can avoid adverse effects on welding quality.
摘要:The reasons leading to weld joint fracture of the deaerator water system pipe of a nuclear power plant during operation were analyzed by means of morphology analysis,hardness test,metallographic test,SEM and other detection means. The results show that the crack of weld joint of drain pipe is extended and propagation under the alternating load. The high stress and poor quality of welding are the main reasons for the fracture of the pipe weld joint.
关键词:deaerator water system;stress concentration;unfavorable welding;fatigue crack
摘要:In order to characterize the difference of microstructure and properties between oxyacetylene welding and laser cladding of cobalt-based Stellite 6 alloy wear-resistant layer,mature welding parameters are adopted to prepare wear-resistant layer of test plate. The effects of different technologies on the composition,hardness,microstructure and corrosion performance of Stellite 6 alloy coating are studied based on the test plate with wear resistant layer. The results show that for oxyacetylene welding and laser cladding technology,the hardness average value of Stellite 6 alloy coating can meet the acceptance requirements by using mature welding parameters,and no abnormal microstructure is found in metallographic test. By EDS energy spectrum analysis, it is found that the composition segregation of wear-resistant layer is obvious under the condition of oxyacetylene welding technology,especially the formation elements of hard particles such as C,W and so on. Under specific working condition,the electrochemical corrosion test shows that the passivation effect of wearresistant layer is more obvious under the condition of laser cladding.
摘要:The full-scale simulation experiment of the main pipeline installation is the most important work before the main installation and welding of the main pipeline of the nuclear power plant,and the backing welding is the first process of welding. The quality is the basis for ensuring the weld molding and performance of the main pipeline. As a consequence,controlling the quality of the backing welding is the key to the success of the full-scale simulation experiment of the main pipeline. This paper is mainly aimed at the burnthrough,concave and non-welding defects occurred in the three-weld backing welding process of the main pipe of a nuclear power plant. It is analyzed from five aspects:human,machine,material,method and ring. And combined with the test verification after the cause analysis,find out the shortcomings in the simulation of the trial,make clear the quality control measures of the main pipe backing welding and provide some guidance for the follow-up of the main pipeline work.
SHI Xianchao,SHI Yu,ZHANG Gang,WANG Kaifei,SUN Qingling
Vol. 49, Issue 4, Pages: 153-158(2019)
摘要:Medium-thick 16MnR steel plate has the advantages of high strength and good plastic,and is commonly used for the special manufacture of storage container for nuclear waste. However,there are some disadvantages of welding the medium-thick 16MnR steel plate by using the traditional root welding procedure with backing plate, including low efficiency,complicated process and instable quality of appearance of weld. Based on this problem,the plasma arc welding and low/high frequency pulse TIG welding are used to realize double-sided forming of single-sided welding of 16MnR steel plate without backing plate. The experimental research shows that the double-sided forming of single-sided welding with 8 mm thick blunt edge can be realized by the wire-filling plasma welding procedure,and the defect-free appearance of weld is obtained,but its parameter adjustment interval is narrow,the welding process is tend to lose stability when facing small fluctuation in the production process;When using low-frequency pulsed DC TIG welding,the full penetration of the 5 mm thick blunt edge can be stably realized,the front surface of the weld shows fish scale pattern with a large gap,and the weld heat affected zone has more lath martensites,which increases the strength and toughness of weld. When using high-frequency pulsed DC TIG welding,the welding heat input reduces,the arc obviously shrinks,and the penetration increases,the maximum penetration of 7 mm can be welded. With the stable welding process and high welding efficiency,there are many wedmanstatten structures in the weld zone and the fusion zone,and numbers of lower bainite structure with better toughness at low temperature in the heat affected zone.
关键词:plasma arc welding;pulse TIG welding;arc shape;appearance of weld;microstructure
LIU Chengdan,LI Chaowei,WANG Chenglin,ZHANG Mingke,XUE Jingkai,FANG Li
Vol. 49, Issue 4, Pages: 159-163(2019)
摘要:The changing type of globe valve for class 1 components of nuclear power unit involves massive pipeline welding. During the overhaul of Fanjiashan nuclear power unit 1 and 2,the automatic welding is used to achieve the changing type of 56 manual globe valves. Due to strict weld quality requirement and short construction period,the changing type of globe valve has become a huge challenge. The quality control points of automatic welding construction on site are summarized,and it is pointed out that elaborate construction and comprehensive technological explanation are key to ensuring valve pipeline welding. For the purpose of the good quality of welding,the reasonable and practical operation guidance,technological explanation and quality control measures are established,which provides valuable experience for automatic welding of pipeline for nuclear power plant.
关键词:manual globe valve;stainless steel;automatic welding;quality control
摘要:Low-alloy steel electrode CHE608HR is used for support of nuclear steam generator. Adopting PWHT temperature of 620 ℃ with different PWHT holding times,the influence of postweld heat treatment(PWHT) holding time on the mechanical properties and microstructure of weld metal is studied by metallographic microscope. The results show that as PWHT holding time increases,the tensile strength of deposited metal reduces and impact property at low temperature rises at first and then decreases. Wtih the PWHT holding time of 1~24 h,good comprehensive mechanical properties of deposited metal can be obtained.
ZOU Guowei,MA Peifeng,WANG Weibo,LI Zhijie,FANG Disheng
Vol. 49, Issue 4, Pages: 168-172(2019)
摘要:According to reactor pressure vessel stainless steel cladding qualification,this paper conducted stainless steel cladding by single TIG and twin-electrode TIG,respectively. The main difference between double tungsten and single tungsten is illustrated by investigating and comparing the weld formation,metallographic structure,hardness distribution,chemical composition,impact properties and intergranular corrosion. Results show that both twin-electrode TIG and single TIG can produce excellent weld bead formation,but the efficiency of twin-electrode TIG cladding is much higher. And the weld bead properties produced by the two methods are similar.Twin-electrode TIG cladding process has been applied to the manufacture of reactor pressure vessels.
摘要:Taking the on-site assembly and welding of the steel containment vessel of a nuclear power plant as an example,this paper introduces the composition of the steel containment vessel of a nuclear power plant,the welding characteristics of SA738Gr.B material,difficulties in the construction process,welding process,common methods for controlling welding deformation,etc. Combining with the characteristics of the structure of the steel containment vessel,the reasons of welding deformation during assembling and welding of steel containment vessel are analyzed. Taking the assembling and welding of bottom head of steel containment vessel as an example,the measures for controlling the welding deformation of the bottom head are described from the groove design,the gap of the groove group,the amount of misalignment,the tack welding and the welding process and so on,the practical results show that the proposed measures of welding deformation is feasible. It provides a reference for the welding deformation control of steel containment in nuclear power plant.
关键词:nuclear power plants;steel containment;SA738Gr.B steel;welding deformation
摘要:In view of the characteristics of large internal back arc transition curvature and bending and torsion of autonomous nuclear power hollow blades in CAP1400,its internal back arc forming mold and thermoforming technology are key to ensure the manufacturing accuracy of the blade. According to the structural characteristics of the internal back arc profile,a reasonable thermoforming mold is designed by using the finite element simulation analysis. The thermophysical performance result of JMatPro is simulated and analyzed with Autoform by thermodynamic coupling, and a reasonable hot pressure technology for internal back arc forming is finally worked out to realize the forming of complex multi-dimensional hollow blades and ensure the manufacturing accuracy of nuclear power hollow blades.
摘要:Fuel assembly is the core elements of chain reaction in nuclear power systems. Its structural stability and reliability are critical to the safety of nuclear power operation. Nuclear power plant has high requirements for the welding performance and corrosion resistance of nuclear austenite stainless steel,which is the main component of the nuclear fuel skeleton. At present,most nuclear austenite stainless steels for reactor core parts of nuclear power plant rely on import. This is not good for national nuclear safety. From the angle of the welding performance of domestic nuclear austenite stainless steel for reactor core part,Firstly,three modification experiments are carried out on the trial-produced domestic materials,and the idea of improving welding performance is obtained. Then,for insufficient welding performance of domestic materials,a special welding technology suitable for domestic materials is developed.The new technology utilizes the thermal stress produced by the special geometric structure of weld heat affected zone to restrain the movement of metal in molten pool,thus improving the welding performance of domestic materials. This developed welding technology has passed all kinds of technical evaluation and has been successfully applied to the localization of nuclear fuel assembly manufacturing in the HPR1000. The research results are greatly significant for improving the welding performance and quality of domestic nuclear fuel assembly parts.
CUI Bing,LI Zhuyuan,HAO Qian,LIU Jinping,XU Jiajie
Vol. 49, Issue 4, Pages: 191-195(2019)
摘要:With the high measurement accuracy,wide range and direct output in the form of voltage(or current),ZrO2 ceramic oxygen sensor has an important application prospect in the new type nuclear reactors. However,due to the characteristics of ZrO2 ceramic material and special application environment,it is necessary to carry out a reliable joining of ZrO2 ceramic with itself or metals to realize the complementary advantages. The joining characteristics and present joining methods of ZrO2 ceramics in the field of nuclear power are summarized. The characteristics of each joining method are discussed,and the development direction of ZrO2 ceramic joining technology is pointed out.
摘要:For the problem of leak of stainless steel overlay in fuel transfer tank of a nuclear power plant in China,the liquid penetration test,vacuum foaming method,layered water test,reverse osmosis method and helium leak detection method are used to find the leak point successfully. Helium leak detection method successfully locates the leak point once,and the causes of missed inspection of liquid penetrant inspection,water-bearing test and reverse osmosis method are analyzed. Combining the principle features of various methods,the advantages and disadvantages of various methods are compared and analyzed,and the notes for use are given. The fuel transfer pool leak detection has the characteristics of large inspection scope,high radiation dose,limited working time,and need to locate leak point as soon as possible,an effective workflow for leak detection of stainless steel overlay in fuel transfer tanks is proposed,which provides reference for leak detection work of similar structures such as spent fuel pool,reactor pool and internal component pool.
摘要:A series of reserved TIG welding experiments are carried out on a 3 mm thick 304 stainless steel plate. A clear image of the front fusion hole is captured by the CMOS vision detection system. By MATLAB image processing tool,the image processing algorithm in line with the characteristics of the fusion hole image is designed,the fusion hole-gap edge is gained,and the widths of the fusion hole and gap are calculated. The results show that the welding parameter window with stable fusion hole is relatively narrow,and the fusion hole can only maintain 4~5 s without adjustment in most cases. When the welding speed is constant,the welding current and the reserved gap are the important factors affecting the size of the fusion hole. Other parameters remain unchanged,the width of the fusion hole increases as the welding current increases;the width of the fusion hole also increases as the reserved gap increases,and shows a similar change rule.
摘要:For the problems of the ductility dip cracking(DDC) susceptibility of deposited metal of 690 nickel base alloy at high temperature,a strain-to-fracture(STF) test based on Gleeble-3500 thermo-mechanical simulator is performed to evaluate the DDC susceptibility of WHS690M and Inconel 52 M. The results show that the minimum critical strain of the DDC of deposited metal appears at the temperature about 1 050 ℃,and welding heat input has little effect on the minimum critical strain. Comparing with the deposited layer of large-area surfacing,the critical strain of butt weld deposited metal reduces,and DDC susceptibility increases.
摘要:The microstructure and mechanical properties of EAM16MND5 steel by electrical additive manufacturing were investigated by electrical additive manufacturing in eight different heat treatment parameters by the number of thermal cycles,the temperature,holding time and the kind of heat treatment factors. The experimental results showed that the strength of the material was changed less in different thermal cycles or the temperatures of heat treatment after stressrelieving heat treatment. The effect of the holding time on simulated stress relieving heat treatment was less for material strength,but more for impact ductility,and the impact ductility was more excellent for the material with second stress relieving heat treatment than the first. The carbide was diffusing to the intergranular and assembling during stress relieving heat treatment and simulated stress relieving heat treatment.
摘要:Thin-walled stainless steel pipes are widely used in auxiliary systems of nuclear power stations. They are important items in nuclear power welding in service,and their welding quality affects the operation quality of nuclear power plants.This paper mainly introduces the welding technology characteristics and difficulties of thin-walled stainless steel pipes with large diameter in nuclear power stations. It is emphasized that the welding quality of large diameter stainless steel thin-walled pipe can be ensured by the selection of argon chamber,the validation of effect,the use of appropriate pipe group,the adoption of appropriate welding methods and process parameters,and the key point validation in the welding process. This method has been applied in many nuclear power stations in Guangdong Nuclear Power Group of China and has good applicability.
关键词:maintenance of nuclear power station;thin-walled stainless steel pipes;welding;argon space;quality control
摘要:As an important part of the third barrier of nuclear safety, nuclear island steel lining is commonly pieced together by PC and PF shielded metal arc welding(SMAW) technology,which is the key and difficult point of quality control of nuclear island civil construction. The effects of different welding procedures and welding positions on chemical composition,microstructure and mechanical properties of welded joints are studied. The results provide a theoretical basis for the feasibility of the application of tungsten inert gas welding(TIG) in the nuclear island steel lining,which forms a whole set of new type welding procedures development ideas.
关键词:nuclear island;steel lining;tungsten inert gas welding;weld inspection;welded joint property
摘要:By analyzing the welding technology problems in the installation and construction of nuclear power plants,a cantilever automatic welding technology scheme is proposed to improve the pipeline prefabrication efficiency and ensure the welding quality. The feasibility of the scheme is demonstrated from the aspects of welding cost,welding efficiency,welding quality and welding safety. The results show that the cantilever automatic welding technology has higher superiority than manual welding technology,and it is completely feasible.
摘要:Due to excellent corrosion resistance and weldability and low linear expansion coefficient,the duplex stainless steel is very suitable to be use as the corrosion resistant lining for carbon steel and low alloy pressure vessel. According to the weldability of the materials,using a variety of welding methods and material forms with austenitic stainless steel welding materials 308L & 309L to simulate the common type of joint of the products. The duplex stainless steel S22253 & S22053 are welded and the tests are performed,such as visual inspection,NDT,tensile test,bend test and room-temperature impact test. The results show that by using austenitic stainless steel welding material,the weld joint of duplex stainless steel has excellent weldability and its all properties meet the requirements.
摘要:The reasons leading to interior leakage of the manual globe valve used in a nuclear power plant during operation was analyzed by means of morphology analysis,hardness test,metallographic test,SEM and other detection means. The results showed that the metal loss of valve base and valve seal surfacing occured under the action of high temperature and high pressure gas-liquid flow,and the poor quality of surfacing on the sealing surface accelerates the internal leakage of the valve. It is recommended to strictly control the quality of the valve,especially the quality of sealing surface,to ensure that the size of the surfacing layer can meet the product design requirements.
关键词:globe valve;interior leakage;valve seal surfacing;erosion
摘要:Containment vessel bottom head(CVBH),assembled and welded on nuclear power project sites,is a petal-shaped ellipsoidal structure featured by large size,thick walls,multiple curvatures,and high precision,which is adopted by China’s nuclear power industry for the first time. The steel plate formed by special equipment through compression molding on the basis of different radii of curvature has large residual stress. Besides,the number of steel plates constituting each ring is different. These characteristics lead to different welding shrinkage and deformation for each ring and make it difficult to reserve a proper welding shrinkage gap. All these increase the difficulty of the assembling and greatly affect the control of the overall dimensions of the CVBH. Therefore,suitable assembly methods and welding deformation control become an important part of the construction process. This paper studies the two types of assembly,welding sequence,anti-deformation welding fixtures,welding processes and other measures of CVBH in three types of nuclear power reactors. Through such introduction and analysis,this paper has validated that the two types of assembly are both feasible and proposed the direction of improvement for the top-down assembly method.
关键词:steel containment;CVBH;assembly;deformation control
摘要:Socket welding joints of instrumentation pipes have the risk of fatigue cracking failure in nuclear power plants during long service period. The quality of these joints is related to the safe operation of nuclear power plants. This paper presented the basic requirements of design of socket welding joints of instrumentation pipes from the aspects of suitable application,axial clearance before welding,welding process during welding,leg sizes and non-destructive tests after welding,etc. At the same time,the corresponding welding technology measures were put forward based on these requirements,and adopting these measures would ensure that socket welding joints of instrumentation pipes would be in long-term reliable service. It can provide recommendable technical guideline for normalized designing and manufacturing of socket welding joints of instrumentation pipes.
关键词:nuclear power plant;instrumentation pipe;socket welding;design
WANG Meng,CHEN Bo,CHEN Peiyin,HUO Shubin,GUO Xiao,LIU Jinxiang
Vol. 49, Issue 4, Pages: 254-257(2019)
摘要:Reactor coolant pump is made of 316 austenitic stainless steel. The stainless steel electrodes in reactor coolant pump are still dependent on imports,which seriously restricts the development of nuclear power business in China. The newly developed WE316HR electrode has excellent comprehensive performance. And deposited metal has good strength,impact toughness and corrosion resistance in the as-welded state,heat-treated state and aging state. It can be used for reactor coolant pump.
摘要:An imported high voltage electron beam welder is the key equipment of processing products. It is equipped with a single station NC turntable,which has long welding preparation time and can only weld one piece. In order to solve the production bottleneck,a welding turntable with ten stations is developed. This turntable has been successfully put into the batch production and processing for more the one year. The solution of mechanical structure,electrical circuit and overall precision of turntable in design process are introduced and good use effect is gained.
关键词:special welding NC turntables with ten stations;vacuum welding;Siemens 840D;herringbone synchronous belt
摘要:According to the welding characteristics of nickel-based alloy 690,the welding current,welding voltage,welding speed,wire feeding speed and the form of tungsten pole are analyzed and controlled through a large number of experiments. The hot cracks and side wall unfusion defects of nickel-based alloy 690 pre-surfacing and safe end-ring welding are avoided. The test process parameters were validated and successfully applied to the welding of the pre-pile surfacing and the safety end ring of Sanmen 2#AP1000 evaporator.
摘要:Main feed water control valve is a very important nuclear safety control valve in the nuclear power plant. In order to enhance the wear resistance of the sealing surface,it is necessary to perform build-up welding on the contact sealing surfaces of the valve with Stellite alloy. The advantages of plasma build-up welding are easy to realize automation,high production efficiency,low labor intensity and low weld dilution rate. It can greatly improve the surfacing production efficiency and welding quality. In this article,the reasons of cracking in Stallite build-up welding of sleeve of main feed water control valve are analyzed,and welding quality control measures are proposed. It can provide useful reference for domestic valve manufacturers to surfacing cemented carbide.
摘要:Taking the spent fuel pool of one domestic nuclear power station currently under construction for example,the application of automatic argon tungsten-arc welding process to the stainless steel liner of spent fuel pool has been studied. By verification of type selection,groove design and welding parameters of welding materials,and consideration of actual application condition on site,it shows that the performance of welding joint can meet the requirements of nuclear power design standard,and this technology can effectively improve welding quality and efficiency compared with traditional manual argon arc welding method.
关键词:nuclear power station;stainless steel coating;automatic TIG welding
摘要:There are two pairs of double-layer thick forged plates welding on the shell as horizontal supports in a certain third-generation steam generator. The welding seam length is 1 900 mm,and the welding seam thickness is 130 mm. After welding,the roundness of the shell should be less than 5 mm,and the parallelism of the upper and lower surface of the horizontal support should be less than 1.5 mm. It is difficult to control the deformation because of the high welding stress. Through the analysis of the welding deformation of the horizontal support,a set of welding groove with narrow gap is designed. The rational welding sequence of the alternate welding is set. We use narrow gap submerged arc welding method. The deformation control measures such as anti-deformation tooling is used to effectively control the welding deformation and ensure the parallelism of horizontal support and roundness of the shell after welding of the horizontal support. According to the analysis of the actual deformation data,the structure of the horizontal support is optimized,and the manufacturing cost of the horizontal support is reduced. The relevant measures in this paper can provide reference for similar thick plate welding deformation control in the future.
摘要:1Cr11Co3W3NiMoVNbNB imported from Japan for the new high-strength martensitic heat-resistant steel,compared with the traditional 12Cr heat-resistant steel,W,Co elemental content increased to 3%,making the steel has better high-temperature lasting strength,creep resistance,but the weldability is deteriorated. In this paper,research on the weldability of 1Cr11Co3W3NiMoVNbNB heat-resisting steel,and conducts oblique Y-groove and cold-plug test respectively. The results show that the preheating temperature is increased,the welding crack rate of oblique Y-groove is gradually decreased,and the preheated bolt sample is not preheated to be intergranular and transgranular fracture morphology. When the preheating temperature reaches 300 ℃,the fracture is ductile fracture morphology. As the preheat temperature increases,the material’s cold cracking sensitivity decreases.
摘要:Through different post-weld heat treatment tests,the effects of different holding time on the properties and microstructure of CHE558HRF deposited metal for nuclear power welding rods were investigated. The results showed that with the increase of post-weld heat treatment time,the tensile strength changed little and the impact energy was significantly improved. Through metallographic structure and electron microscopy analysis,the microstructure of the weld center gradually changed to acicular ferrite with the increase of heat treatment time,and the M-A component attached to the massive ferrite gradually disappeared.
摘要:The reasons of root discontinuity on the tube-to-tube sheet weld test coupon of the steam generator in a domestic improved second generation nuclear power unit are analyzed. The results show that the tube is not being thoroughly cleaned,so something on the tube wall influence the tacking expanding and lead to a excessive gap between the root tube and hole,which is the ultimate reason of the root discontinuity. So the weld test coupon could not represent the production welds. According to the analysis result,corresponding precautionary measures are proposed,which has some reference for the subsequent welding of the tube-to-tube sheet welds.
关键词:improved second generation nuclear power unit;tube-to-tube sheet weld;test coupon;root discontinuity;cause analysis
摘要:The bimetal grid is a major component of nuclear fuel assembly,which belongs to nuclear reactor core product. So the welding quality of Bimetal Grid is of great significance for the nuclear power safety. The electron beam welding process of the bimetal grid is gradually applied to parts manufacturing of PWR nuclear fuel. Because there are many factors affecting the process,so there are many quality assurance measures. Over the years,these scattered quality control methods have not been systematized. According to the stipulation of quality control elements in GB/T 12467-90 and RCC-C 2015,combining with the experience and methods in the supervision of company’s production and quality management summarized over the years,discussions are made on material control,technology management,production site management,welding defects control,product inspection,document control,etc. Finally,a standardized and systematic welding quality control method is developed. In this way,the final product quality and the user satisfaction can be improved.
关键词:bimetal grid;fuel assembly;EBW;quality control
摘要:The interpass temperature plays a decisive role in the welding quality of high strength low alloy steel. Especially for multilayer multi-pass welds,the thermal cycle of weld interacts with each other,and the phase transformation is extremely complex. The effect of interpass temperature on the microstructure and cold crack of HAZ of high strength low alloy steel 16MND5 is systematically studied. The experiments are carried out at the room temperature of 125 ℃,250 ℃ and 400 ℃ respectively. The result show that cold cracks occur only in the coarse grained zone of HAZ(CGHAZ) at room temperature,and the corresponding hardness of CGHAZ is the highest(up to 400 HV). The CGHAZ matrix structures corresponding to the four interlayer temperatures are incompletely tempered martensite,tempered martensite,tempered martensite and lower bainite,and granular bainite respectively. In addition,the widmanstatten appears near the fusion line in CGHAZ obtained from all the interpass temperatures except room temperature,especially at 250 ℃. The preheating temperature of 125~250 ℃ is regarded as the most suitable according to the hardness,microstructure and fracture of welded joints.
摘要:The situation of two Chinese criterions for welding procedure qualification on the class 1,2,3 components are introduced. By comparing and analyzing the welding procedure qualification for corrosion resistant surfacing from the aspects of welding parameters and examination,the differences are found,which provides some reference and guide to solve them and finally obtain the unified welding procedure qualification criterions for the future.
摘要:China Industry 4.0 guides to adopt industrial Internet technology,use the whole system framework of knowledge and information processing brought by the Internet to unite machines and industry,and promote the all-ground trend of industrial production.This paper proposes a new intelligent welding machine design idea that integrates RS422 bus,CAN bus,Wifi communication,and other technologies,so that the welding machine has the interface with Industry 4.0,has the ability of industrial manufacturing interconnection,and realizes the functions of data cloud management,mobile phone APP field control and data offline backup. The welding robot control,welding machine group control,mobile APP control,computer control,cloud data management and other functions are realized through the verification of practical technology.
关键词:Industry 4.0;industrial interconnection;cloud management;internet of things
摘要:At present,manual arc welding is the main welding method for the circumferential seam of steel containment vessel(material is SA738 Gr.B) in CAP1400 nuclear power plant,which is not only inefficiency,but also high cost. The submerged arc horizontal position welding technology test is carried out under the condition of heat treatment and non-heat treatment respectively,and the results of welding material applicability,specimen preparation requirement,nondestructive testing,machining sampling and destructive test are analyzed. The results show that the welding material and reliable submerged arc welding technology adopted can meet the welding technology requirements of SA738 Gr.B steel plate. So the submerged arc horizontal position welding technology can be used for the welding of the circumferential seam of nuclear power plant steel containment vessel.
关键词:CAP1400 nuclear power plant;steel containment vessel;circumferential seam;submerged arc horizontal position welding process
摘要:Reactor internals are the key components of the reactor. They provide support and positioning for nuclear fuel assemblies.They also need to be positioned accurately and prevent fatigue damage caused by fluid vibration. Cobalt-based alloys have good properties of high temperature resistance,fatigue resistance,wear resistance and so on. They are ideal contact materials for positioning.There are many defects in cobalt-based alloy surfacing of reactor internals in a nuclear power project,which also leads to the scrap of individual parts. The wear resistance mechanism of cobalt-based alloy is introduced,and the causes of defects are analyzed from various factors of surfacing.
摘要:Two kinds of assembly and welding methods of three-stage nuclear power project CV bottom head are introduced,compare and analyze the two methods from the demand amount for auxiliary fittings and the install removal mode,welding space and welding method,the amount of cutting,etc. The result shows that adopt the Backward Assembly of bottom head,the amount of bracket used for assembly will be reduced greatly,which will be help to remove and transport,and the amount of cutting is reduced,in addition with large welding space,which benefit to automatic welding. This paper also analyzes the stress shrinkage and deformation control of weld seam,hoisting and transportating mode,the advantages and disadvantages of the two assembly and welding methods are explored,so as to provide reference for the follow-up similar modules assembly and welding,convenient for the construction company to make full use of its advantages and choose the best assembling and welding method,which can reduce the workload on the basis of ensuring quality.
关键词:CV bottom head;assembly and welding;deformation
WANG Qingtian,HE Peifeng,JIANG Xingjun,WU Bingjie,GONG Yusheng,CHEN Xin
Vol. 49, Issue 4, Pages: 329-332(2019)
摘要:During the welding process of the lower wall cylinder of CRDM anti-seismic bracing structure of HPR1000 integrated surfacing top structure,there are two repairs welded continuously. During the last repairs welded to remove defects,more welding cracks were found,which led to the whole scrap of the lower cylinder. The causes of weld defects in lower cylinder are analyzed in detail,and then measures such as changing the design of weld groove,optimizing welding parameters,changing the position of weld groove and adopting integral forging are taken. The improvement measures proposed in this paper have important reference significance for the following welding of HPR1000 and AP1000 nuclear power unit integrated reactor top structure.
关键词:integrated head structure;lower shroud;welding defect analysis;design improvement
YANG Lin,XIONG Jiankun,WEN Zhongbo,ZHAO Pengfei,XU Jian,HUANG Li,YANG Dong
Vol. 49, Issue 4, Pages: 333-338(2019)
摘要:After assembling and welding of a nuclear power directly-welded diaphragm,a large number of cracks were found in the heat-affected zone(HAZ) at the steam inlet and exit sides of the blade convexity by penetration inspection. In this paper,the thermalmechanical coupling calculation of this structure is carried out by SYSWELD,the crack initiation mechanism was analyzed,structural stress,transformation stress and hardened structure are the fundamental causes of delayed crack in the HAZ of the blade. It is clear that the excessive manual grinding of groove is likely to cause the penetrating crack along the thickness direction of the blade;vicarious optimized welding procedures are simulated,the results show that the structural stress,transformation stress and hardened structure are all improved to some extent,a special welding procedure adapting intermediate heat treatment,preheating,post-heating and four-stage cross welding sequence is proposed,the surface stress in the HAZ of the blade will be reduced by about 260 MPa,which will greatly lower the delayed crack tendency of the subsequent diaphragms.
摘要:Based on the characteristics of metal 3D printing technology,the research and application status of metal 3D printing technology in the field of nuclear power are analyzed. At present,the research and application of this technology in the field of nuclear power is still at the initial stage,which is limited to the manufacture of prototype parts and the in-service replacement of non-key components,and the technical application of key nuclear-level components has not been really realized. According to the characteristics of nuclear power components and the special requirements of functional service,the key problems and preliminary solutions of metal 3D printing technology in the field of nuclear power are summarized. Combining with the characteristics of 3D printing technology and the actual needs of power plants,the application prospect analysis is carried out.
关键词:3D printing;nuclear power equipment;in-service replacement;welding repair
摘要:Taking austenitic stainless steel Z2CND18-12(AC) used in nuclear power instrument tanks as the test object,the difference between automatic pulse TIG welding and GTAW welding is studied,including weld appearance in welding process and after welding,girth welding shrinkage,weld reinforcement and surface flatness,and the macroscopic metallography,microstructure and mechanical properties of welded joints. The results show that pulsed TIG welding has smaller welding shrinkage,better weld surface smoothness,more uniform weld microstructure distribution,smaller grain size,and better weld strength,plastic toughness and deformation resistance.
LIU Wei,LIU Xiurong,YANG Zuoyong,YANG Xiaoyu,ZHANG Yanfen
Vol. 49, Issue 4, Pages: 350-351(2019)
摘要:Welding operations are complicated in nuclear power plant equipment manufacturing company,due to various welding content,different workshops and different welding procedures correspond to different welding methods and difficulties. By looking for an accounting method that can calculate the workload under the same standard,the big data management of different workshops and different welding work progress are realized,a fair workload accounting method are found and given back to the welder’s performance appraisal,which effectively improves the welder’s working enthusiasm and lays the foundation for improving the quality and reducing the manufacturing cycle of the nuclear power equipment product.
摘要:With its large structure size(the outer diameter of inserted plate is 8.5 m),narrow interval(595~620 ℃) of the post-welding heat treatment(PWHT),and major difference of plate thickness(the thickness of dome head is 36 mm,the thickness of insert plate,penetration sleeve as well as flange are all 130 mm),the PWHT process for equipment hatch is a big challenge. In this paper,the temperature uniformity of heat treatment furnace is measured to establish an effective heating area,which guarantees the precision range of heat treatment temperature. In this area,PWHT tests for module of dome head and flange and module of insert plate and penetration sleeves are carried out in furnace. The analysis results of tests procedure and heat treatment curves provide theoretical and data support for CAP1400 large penetration assembly PWHT.
摘要:Base on the research of repair technology on seal welding defects of non-regenerative heat exchanger tube to tube plate in nuclear power plant,the process and technical requirements of repairing defects are introduced in this paper. The successful application of the repair welding technology of the first pass self-fluxing and the second filler wire in the repair engineering of seal welding defects of the tube to tube plate has guaranteed the welding quality,promoted the weld forming and improved the maintenance efficiency.This technology can realize the on-line repair of seal weldind defects on heat exchanger tube to tube plate and provide an important reference for the following similar work.
摘要:The large thick wall equipment tube(52 mm at the thinnest part of the plate) was affected by constraints and environment during the construction process,and the traditional technology method and Fangfashigong caused cracks in the weld seam. In this paper,we describe the cracks in three stages of welding,bottom beating and post-welding heat treatment during the construction of large thick wall equipment,analyze the environmental factors,construction technology and Shigongfangfa,and formulate effective improvement measures. The method of increasing the density of positioning welding,the thickness of positioning welding,the slow cooling after welding,and adjusting the process control of the number of segmental heat treatment are used to avoid the crack defects again. It can avoid the crack defects in the subsequent welding activities of the equipment cylinder,and it can provide effective experience for the subsequent assembly activities of the similar thick wall equipment,and ensure the smooth completion of the welding energy and quality of the large thick wall weld group in the relevant fields.
关键词:position welding;slow cooling after welding;heat treatment subsection;weld cracking
摘要:The paper introduces the applications of AWS series D welding standards in the construction of some nuclear power project,presenting comparisons on their governing boundaries with exemplifications,and giving analysis on their accordance and compatibility amongst each other,moreover,it explains governing boundaries between AWS series D standards and relevant ASME codes,all of which can provide a certain reference for optimizing domestic standardized system in nuclear power industry.