Abstract Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.
{"title":"Updating risk model for SGTR accident based on success criteria analysis","authors":"M. Mohammadnia, S. M. Hoseyni, Kaveh Karimi","doi":"10.1515/kern-2022-0007","DOIUrl":"https://doi.org/10.1515/kern-2022-0007","url":null,"abstract":"Abstract Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"1 1","pages":"398 - 408"},"PeriodicalIF":0.5,"publicationDate":"2022-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83129735","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract In this study, graphene nanofluids were used to explore the effect of various concentrations on boiling heat transfer of downward-facing heating. Five concentrations of graphene nanofluids were prepared for pool boiling heat transfer experiments. The experimental results show that when the mass concentration is 10 mg/L, the maximum enhancement of the CHF is up to 76.1%. In order to explore the mechanism of graphene nanofluid enhancing boiling heat transfer, after the experiment, the wettability and roughness of the heating surface were measured and the heating surface was characterized by a scanning electron microscope (SEM) and electronic differential system (EDS). The results show that the wettability is enhanced and the surface roughness is reduced. In addition, boiling curves (the curves of heat flux with surface superheat) and the curves of heat transfer coefficient with heat flux at different concentrations have also been observed to further explore the mechanism of enhanced heat transfer.
{"title":"The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface","authors":"Shiqi Wang, H. Hsieh, Zhibo Zhang, Yuan Gao, Zhe Zhou, Jia Gao","doi":"10.1515/kern-2022-0028","DOIUrl":"https://doi.org/10.1515/kern-2022-0028","url":null,"abstract":"Abstract In this study, graphene nanofluids were used to explore the effect of various concentrations on boiling heat transfer of downward-facing heating. Five concentrations of graphene nanofluids were prepared for pool boiling heat transfer experiments. The experimental results show that when the mass concentration is 10 mg/L, the maximum enhancement of the CHF is up to 76.1%. In order to explore the mechanism of graphene nanofluid enhancing boiling heat transfer, after the experiment, the wettability and roughness of the heating surface were measured and the heating surface was characterized by a scanning electron microscope (SEM) and electronic differential system (EDS). The results show that the wettability is enhanced and the surface roughness is reduced. In addition, boiling curves (the curves of heat flux with surface superheat) and the curves of heat transfer coefficient with heat flux at different concentrations have also been observed to further explore the mechanism of enhanced heat transfer.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"17 1","pages":"484 - 494"},"PeriodicalIF":0.5,"publicationDate":"2022-06-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80984265","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract In the current work, the pressure drop of the refrigerant flow in smooth and micro-fin pipes has been modeled with artificial neural networks as one of the powerful machine learning algorithms. Experimental analyses have been evaluated in two groups for the numerical model such as operation parameters/physical properties and dimensionless numbers used in two-phase flows. Feed forward back propagation multi-layer perceptron networks have been developed evaluating the practically obtained dataset having 673 data points covering the flow of R22, R134a, R410a, R502, R507a, R32 and R125 in four different pipes. The outputs acquired from the artificial neural network have been evaluated with the target ones, and the performance factors have been estimated and the prediction accuracy of the network models has been resourced comprehensively. The results revealed that the neural networks could predict the pressure drop of the refrigerant flow in smooth and micro-fin pipes between 10% deviation bands.
{"title":"Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method","authors":"A. B. Çolak, A. Celen, A. S. Dalkılıç","doi":"10.1515/kern-2022-0037","DOIUrl":"https://doi.org/10.1515/kern-2022-0037","url":null,"abstract":"Abstract In the current work, the pressure drop of the refrigerant flow in smooth and micro-fin pipes has been modeled with artificial neural networks as one of the powerful machine learning algorithms. Experimental analyses have been evaluated in two groups for the numerical model such as operation parameters/physical properties and dimensionless numbers used in two-phase flows. Feed forward back propagation multi-layer perceptron networks have been developed evaluating the practically obtained dataset having 673 data points covering the flow of R22, R134a, R410a, R502, R507a, R32 and R125 in four different pipes. The outputs acquired from the artificial neural network have been evaluated with the target ones, and the performance factors have been estimated and the prediction accuracy of the network models has been resourced comprehensively. The results revealed that the neural networks could predict the pressure drop of the refrigerant flow in smooth and micro-fin pipes between 10% deviation bands.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"24 1","pages":"506 - 519"},"PeriodicalIF":0.5,"publicationDate":"2022-06-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78461160","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract With the release of reports such as NUREG/CR-6850, the calculation of ignition frequency concerning general large-scale Pressurized Water Reactors (PWRs) has matured. However, there is currently a lack of methods for calculating the ignition frequency in the case of Small Modular Light Water Reactors (SMRs). By studying the calculation of ignition frequency reported in NUREG/CR-6850, we propose a method for calculating the ignition frequency in SMRs, which is based on the generic ignition frequency at the component level. The problem of counting ignition sources is discussed in detail, and we determine the component-level ignition frequencies due to different types of ignition sources. In order to improve the calculation of the ignition frequency in SMRs, this paper provides two methods, which are based on the prior lognormal distribution and the prior Gamma distribution, respectively, for updating ignition frequency. We also consider the effect of the accumulation of fire events on the posterior mean determined by both methods. In this paper, we suggest that the method based on the prior lognormal distribution should be used in the initial stage of updates of ignition frequency. As data for plant-specific events accumulate, the approach based on the prior Gamma distribution should be considered.
{"title":"The analysis of fire ignition frequency calculation for small modular light water reactors","authors":"Hongxia Jiang, Zihan Liu, C. Peng","doi":"10.1515/kern-2022-0030","DOIUrl":"https://doi.org/10.1515/kern-2022-0030","url":null,"abstract":"Abstract With the release of reports such as NUREG/CR-6850, the calculation of ignition frequency concerning general large-scale Pressurized Water Reactors (PWRs) has matured. However, there is currently a lack of methods for calculating the ignition frequency in the case of Small Modular Light Water Reactors (SMRs). By studying the calculation of ignition frequency reported in NUREG/CR-6850, we propose a method for calculating the ignition frequency in SMRs, which is based on the generic ignition frequency at the component level. The problem of counting ignition sources is discussed in detail, and we determine the component-level ignition frequencies due to different types of ignition sources. In order to improve the calculation of the ignition frequency in SMRs, this paper provides two methods, which are based on the prior lognormal distribution and the prior Gamma distribution, respectively, for updating ignition frequency. We also consider the effect of the accumulation of fire events on the posterior mean determined by both methods. In this paper, we suggest that the method based on the prior lognormal distribution should be used in the initial stage of updates of ignition frequency. As data for plant-specific events accumulate, the approach based on the prior Gamma distribution should be considered.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"23 1","pages":"409 - 419"},"PeriodicalIF":0.5,"publicationDate":"2022-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85274100","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. Quddus, Ajmal Shah, K. Qureshi, M. K. Ayub, M. Iqbal, A. Samee
Abstract The direct contact condensation (DCC) of steam in subcooled water encounters in wide range of the industrial applications. On one side, it is an efficient and rapid, mass and heat transfer phenomenon. But, on the other side, it may generate condensation induced water hammers (CIWH) events which may cause high pressure peaks resulting in severe damage to the mechanical systems. This computational study intends to explore the underlying physics of CIWH events while injecting subcooled water into steam filled horizontal pipe section. The Reynolds number is varied from, Re w = 60,750 to 646,900, to study the flow regimes (stratified and slug), onset of CIWH and local flooding conditions. The results have been compared with the published data and found in good agreement. It has been observed that for Re w = 182,300, flow remains stratified. However, the flow regime changes from stratified to slug flow at Re w = 303,850–646,900, possibly due to the onset of CIWH. Extensive steam pockets have been observed at Re w = 303,850, which may be considered as onset of CIWH. Local flooding condition is also started at Re w = 303,850 and is observed to be shifted upstream with the increase in Reynolds number. This study is considered to be useful for the safe design and economical operation of the relevant systems in nuclear and other related industry.
{"title":"Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers","authors":"A. Quddus, Ajmal Shah, K. Qureshi, M. K. Ayub, M. Iqbal, A. Samee","doi":"10.1515/kern-2021-1061","DOIUrl":"https://doi.org/10.1515/kern-2021-1061","url":null,"abstract":"Abstract The direct contact condensation (DCC) of steam in subcooled water encounters in wide range of the industrial applications. On one side, it is an efficient and rapid, mass and heat transfer phenomenon. But, on the other side, it may generate condensation induced water hammers (CIWH) events which may cause high pressure peaks resulting in severe damage to the mechanical systems. This computational study intends to explore the underlying physics of CIWH events while injecting subcooled water into steam filled horizontal pipe section. The Reynolds number is varied from, Re w = 60,750 to 646,900, to study the flow regimes (stratified and slug), onset of CIWH and local flooding conditions. The results have been compared with the published data and found in good agreement. It has been observed that for Re w = 182,300, flow remains stratified. However, the flow regime changes from stratified to slug flow at Re w = 303,850–646,900, possibly due to the onset of CIWH. Extensive steam pockets have been observed at Re w = 303,850, which may be considered as onset of CIWH. Local flooding condition is also started at Re w = 303,850 and is observed to be shifted upstream with the increase in Reynolds number. This study is considered to be useful for the safe design and economical operation of the relevant systems in nuclear and other related industry.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"126 1","pages":"470 - 483"},"PeriodicalIF":0.5,"publicationDate":"2022-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87855019","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract A heat pipe transfers heat effectively between two solid surfaces by incorporating the principles of the transition of phase and thermal conductivity. The study aims to investigate the thermal characteristics of a cylindrical heat pipe and the various factors affecting its performance. The effect of different working fluids, i.e., water, ethanol, and methanol, wick material, i.e., copper and stainless steel, and angle of inclination varied from varied between 0° and 90°. The fill volume is also varied from 20 to 40% to analyze the thermal resistance and effective thermal conductivity of the heat pipe. The optimum value of angle of inclination is found to be 60° at 30% fill volume of working fluid irrespective of the wick material.
{"title":"Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions","authors":"Nidhi Nigam, A. Patil, M. Kumar","doi":"10.1515/kern-2022-0008","DOIUrl":"https://doi.org/10.1515/kern-2022-0008","url":null,"abstract":"Abstract A heat pipe transfers heat effectively between two solid surfaces by incorporating the principles of the transition of phase and thermal conductivity. The study aims to investigate the thermal characteristics of a cylindrical heat pipe and the various factors affecting its performance. The effect of different working fluids, i.e., water, ethanol, and methanol, wick material, i.e., copper and stainless steel, and angle of inclination varied from varied between 0° and 90°. The fill volume is also varied from 20 to 40% to analyze the thermal resistance and effective thermal conductivity of the heat pipe. The optimum value of angle of inclination is found to be 60° at 30% fill volume of working fluid irrespective of the wick material.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"13 1","pages":"375 - 384"},"PeriodicalIF":0.5,"publicationDate":"2022-06-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82463891","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract This paper presents a newly developed steady state core thermal hydraulic model (named SSTH-RR10 model) for upgrading the Egyptian first Research Reactor (ETRR-1), from its original power of 2 MWth to a higher level of 10 MWth, by considering different types of nuclear fuels. The SSTH-RR10 model is capable to predict and calculate, by means of a developed computer program, all the steady state thermal hydraulic parameters for the defined core configuration for each fuel type at 10 MWth. Three different fuel types were investigated: the reference fuel EK-10 rod type, the MTR plate type, and the IRT-4M ducted type. For each fuel type, the distribution of central fuel, clad, and coolant temperatures for average and hot channels of the core were predicted in the axial direction. Power distributions and pressure gradients were predicted as well. Moreover, the program calculates the safety limits and margins against the critical phenomena encountered such as the Onset of Nucleate Boiling (ONB), Departure from Nucleate Boiling (DNB), and the Onset of Flow Instability (OFI). Results of the SSTH-RR10 program for benchmarks of powers of 2 and 10 MWth are verified by comparing it with the published results of the International Atomic Energy Agency (IAEA), and those published for other programs such as PARET code, and very good agreement is found. The safety margins against ONB and DNB were evaluated in which the minimum DNB ratio was found to be about 3.1, which gives a sufficient margin against the DNB. The present work gives confidence in the model results and applications.
{"title":"Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading","authors":"S. Ibrahim, M. Esawy, Hossam I. Yousif","doi":"10.1515/kern-2022-0003","DOIUrl":"https://doi.org/10.1515/kern-2022-0003","url":null,"abstract":"Abstract This paper presents a newly developed steady state core thermal hydraulic model (named SSTH-RR10 model) for upgrading the Egyptian first Research Reactor (ETRR-1), from its original power of 2 MWth to a higher level of 10 MWth, by considering different types of nuclear fuels. The SSTH-RR10 model is capable to predict and calculate, by means of a developed computer program, all the steady state thermal hydraulic parameters for the defined core configuration for each fuel type at 10 MWth. Three different fuel types were investigated: the reference fuel EK-10 rod type, the MTR plate type, and the IRT-4M ducted type. For each fuel type, the distribution of central fuel, clad, and coolant temperatures for average and hot channels of the core were predicted in the axial direction. Power distributions and pressure gradients were predicted as well. Moreover, the program calculates the safety limits and margins against the critical phenomena encountered such as the Onset of Nucleate Boiling (ONB), Departure from Nucleate Boiling (DNB), and the Onset of Flow Instability (OFI). Results of the SSTH-RR10 program for benchmarks of powers of 2 and 10 MWth are verified by comparing it with the published results of the International Atomic Energy Agency (IAEA), and those published for other programs such as PARET code, and very good agreement is found. The safety margins against ONB and DNB were evaluated in which the minimum DNB ratio was found to be about 3.1, which gives a sufficient margin against the DNB. The present work gives confidence in the model results and applications.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"81 1","pages":"452 - 469"},"PeriodicalIF":0.5,"publicationDate":"2022-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74243174","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Siming Guo, Jun Zhang, Lei Shi, Qingwen Chen, Wang Chen
Abstract This article mainly studies the positioning function of radioactive detection technology in process control for processing devices. The accuracy of 22Na detection is not limited by the spatial area by comparing different illumination scenarios; the accuracy of inspection is independent of the accuracy of machining equipment; the accuracy of the detection is not affected by the conditions of the processed body. This study is of great significance for the future radioactive detection technology to make up for the lack of precision caused by the existing sensor technology on the spatial positioning of the processing device, the illumination environment and the material characteristics of the processed body, and for the process control research in the field of advanced manufacturing.
{"title":"Research on the application of 22Na radiolocation detection technology in advanced manufacturing process control","authors":"Siming Guo, Jun Zhang, Lei Shi, Qingwen Chen, Wang Chen","doi":"10.1515/kern-2021-1031","DOIUrl":"https://doi.org/10.1515/kern-2021-1031","url":null,"abstract":"Abstract This article mainly studies the positioning function of radioactive detection technology in process control for processing devices. The accuracy of 22Na detection is not limited by the spatial area by comparing different illumination scenarios; the accuracy of inspection is independent of the accuracy of machining equipment; the accuracy of the detection is not affected by the conditions of the processed body. This study is of great significance for the future radioactive detection technology to make up for the lack of precision caused by the existing sensor technology on the spatial positioning of the processing device, the illumination environment and the material characteristics of the processed body, and for the process control research in the field of advanced manufacturing.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"30 1","pages":"316 - 322"},"PeriodicalIF":0.5,"publicationDate":"2022-05-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82797989","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract The fissile mass deduced from fast neutron multiplicity counting (FNMC) measurement is underestimated if the matrix self-absorption effect of the radioactive source is not taken into account. Based on the analysis of FNMC equations, a set of FNMC system was built to simulate and study the mass attribute of the hollow sphere (spherical shell) plutonium under different shapes and different masses conditions. Geant4 simulation shows that an appropriate parameter correction successfully removes the bias because of the matrix effect. Consequently, the self-multiplication factor, α coefficient and scattering crosstalk of the simulation result were corrected after analyzing the detection efficiency and multiplicity counting rate, and the corresponding polynomial fitting equation was obtained. The corrected mass deviation of samples was less than ±1% in this interval. The results show that the combination of the FNMC and parameter correction can accurately measure the sample mass attribute, which provides a new method for solving similar problems.
{"title":"Improving FNMC for the matrix effect of spherical shell plutonium samples","authors":"S. Hou, Ji-jun Luo","doi":"10.1515/kern-2021-0019","DOIUrl":"https://doi.org/10.1515/kern-2021-0019","url":null,"abstract":"Abstract The fissile mass deduced from fast neutron multiplicity counting (FNMC) measurement is underestimated if the matrix self-absorption effect of the radioactive source is not taken into account. Based on the analysis of FNMC equations, a set of FNMC system was built to simulate and study the mass attribute of the hollow sphere (spherical shell) plutonium under different shapes and different masses conditions. Geant4 simulation shows that an appropriate parameter correction successfully removes the bias because of the matrix effect. Consequently, the self-multiplication factor, α coefficient and scattering crosstalk of the simulation result were corrected after analyzing the detection efficiency and multiplicity counting rate, and the corresponding polynomial fitting equation was obtained. The corrected mass deviation of samples was less than ±1% in this interval. The results show that the combination of the FNMC and parameter correction can accurately measure the sample mass attribute, which provides a new method for solving similar problems.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"23 1","pages":"287 - 297"},"PeriodicalIF":0.5,"publicationDate":"2022-05-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79417140","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Wei Zhang, Hanbo Lin, Jun Tao, Chunhua Bian, Ming-An Hu, F. Xu, Linjun Xie
Abstract The reactor pressure vessel was contact sealed with a double-channel O-ring made of Inconel 718 alloy and nuclear power material SA508. The fretting wear characteristics of Inconel 718 O-tube and SA508 plate friction pair were tested by fretting wear testing machine to explore the failure mechanism of reactor pressure vessel seal system. The test conditions are as follows: normal temperature, normal loads of 10, 20, and 40 N, displacement amplitude of 600 μm, the number of cycles of 10,000, and frequency of 4 Hz. Results show that the coefficient of friction (COF) increased with increasing normal force. Significant material losses were detected during the relative sliding of the contact surface of SA508. A large number of abrasive dust accumulated at the edge of the contact zone, forming a large number of oxides. During the friction of Inconel 718 O-ring, plastic deformation occurred, and a plastic flow layer was formed. The plastic deformation flow at the contact point formed an adhesive connection point, producing adhesive wear and oxidative wear. The wear mechanism was characterized by the combination of oxidative wear and abrasive wear.
{"title":"Frictional wear characteristics of nickel-based alloy and reactor material in pressure vessel reactor","authors":"Wei Zhang, Hanbo Lin, Jun Tao, Chunhua Bian, Ming-An Hu, F. Xu, Linjun Xie","doi":"10.1515/kern-2021-1026","DOIUrl":"https://doi.org/10.1515/kern-2021-1026","url":null,"abstract":"Abstract The reactor pressure vessel was contact sealed with a double-channel O-ring made of Inconel 718 alloy and nuclear power material SA508. The fretting wear characteristics of Inconel 718 O-tube and SA508 plate friction pair were tested by fretting wear testing machine to explore the failure mechanism of reactor pressure vessel seal system. The test conditions are as follows: normal temperature, normal loads of 10, 20, and 40 N, displacement amplitude of 600 μm, the number of cycles of 10,000, and frequency of 4 Hz. Results show that the coefficient of friction (COF) increased with increasing normal force. Significant material losses were detected during the relative sliding of the contact surface of SA508. A large number of abrasive dust accumulated at the edge of the contact zone, forming a large number of oxides. During the friction of Inconel 718 O-ring, plastic deformation occurred, and a plastic flow layer was formed. The plastic deformation flow at the contact point formed an adhesive connection point, producing adhesive wear and oxidative wear. The wear mechanism was characterized by the combination of oxidative wear and abrasive wear.","PeriodicalId":17787,"journal":{"name":"Kerntechnik","volume":"12 1","pages":"278 - 286"},"PeriodicalIF":0.5,"publicationDate":"2022-05-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79961441","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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