Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division最新文献

{"title":"Piping Snubber Failure Experience and Mitigation","authors":"K. L. Saunders, M. Onorato","doi":"10.1115/pvp2022-85167","DOIUrl":"https://doi.org/10.1115/pvp2022-85167","url":null,"abstract":"\u0000 One of the typical characteristics of high temperature piping systems is that they are more flexible. This is due primarily to expansion stress limits which cause the piping designer to add additional elbows and to minimize axial or lateral stops. The resulting high flexibility and low frequency piping system is vulnerable to vibration loading which may result in excessive displacements, and hence, excessive stresses. As a result, designers often add mechanical or hydraulic snubbers to piping systems to mitigate potential vibration displacements. These snubbers work well for infrequent vibration loading such as that from an earthquake. However, operational vibrations have the potential to damage these snubbers and render them ineffective. One such piping system with these supports transfers high temperature crude oil from two furnaces to a large distillation column. The large vibration displacements caused one strut and most of the mechanical snubbers to fail from fatigue loading. There was a concern that the piping itself would eventually fail from fatigue loading and that there would be a loss of the pressure boundary. Our first task was to quantify the magnitude and the type of vibration loading in this piping system. With this information, we could confirm that the observed supports’ damage was caused by the operational vibrations. We next selected and installed viscodampers that are not prone to fail from operational vibration loading. Vibration measurements confirmed the significant vibration reduction after the new style snubbers were installed.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126189954","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario","authors":"N. Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick","doi":"10.1115/pvp2022-84353","DOIUrl":"https://doi.org/10.1115/pvp2022-84353","url":null,"abstract":"\u0000 The US Department of Energy Spent Fuel and Waste Science and Technology (SFWST) program is performing research to determine the mechanical loading conditions applied to spent nuclear fuel (SNF) during normal conditions of transport to inform mechanical tests of SNF and close an important knowledge gap related to the practical disposition of SNF in the US. Researchers at Pacific Northwest National Laboratory (PNNL) have completed an extensive finite element study to characterize and estimate the potential mechanical loads on SNF during a hypothetical 30 cm drop of an SNF transportation package. This modeling study is validated with test data collected by the SFWST program during a physical test campaign that included one-third scale package drop tests and full-scale single fuel assembly drop tests. The test campaign was led by Sandia National Laboratories (SNL) and included international collaboration with Equipos Nucleares S.A, S.M.E (ENSA) and Bundesanstalt für Materialforschung und -prüfung (BAM).\u0000 The key contribution of the modeling study is to go beyond the limitations of the limited number of physical tests to estimate the impact response to variations in impact angle, initial gap conditions, fuel assembly design, burnup and other parameters that affect the mechanical loads. The methodology of this study included a classic parametric study to calculate the impact response of highly detailed fuel assemblies over many combinations of parameters. Models of a 17 × 17 pressurized water reactor fuel assembly and a generic 10 × 10 boiling water reactor fuel assembly were both used in this study to cover the major fuel assembly types in the US inventory. Over 2,000 impact responses were calculated. The results of the parametric study were evaluated using traditional methods and basic statistics. The results were also used to construct a damage model using multiple nonlinear regression techniques to predict the mechanical loads over the full range of all input parameters. The damage model was found to work very well for all impact angle cases where the cask came to rest on its side. It was concluded that end drop cases where the cask remained vertical (instead of tipping over onto its side) were not sufficiently characterized by the current set of parametric study cases to include in the damage model, but it was not a priority to fully investigate that range because the highest mechanical loads were observed in the broader range of side impact cases. This modeling work provides sufficient insight into the mechanical loads on SNF during a hypothetical 30 cm package drop that, when considered along with the physical test data collected by the SNL-led team, the SFSWT program can consider the knowledge gap closed.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"23 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126734080","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario","authors":"Kevin Kadooka, James Fitzpatrick, N. Klymyshyn","doi":"10.1115/pvp2022-84747","DOIUrl":"https://doi.org/10.1115/pvp2022-84747","url":null,"abstract":"\u0000 Packages used to transport spent nuclear fuel (SNF) are required by the U.S. Code of Federal Regulations 10 CFR 71.71 to demonstrate satisfactory performance during a drop scenario. While the CFR is meant to ensure safe package function, it does not evaluate survival of the SNF within. The U.S. Department of Energy Spent Fuel and Waste Science and Technology program is working on closing the knowledge gap related to the response of SNF to external mechanical loads, including the 30 cm package drop scenario in the CFR. In support of this effort, LS-DYNA finite element simulations were developed by Pacific Northwest National Laboratory (PNNL) to model generic drop scenarios at both the package and fuel assembly level. The models were validated against one-third scale package and full scale fuel assembly drop test data and were exercised to predict fuel cladding strains in a narrow range of model configurations.\u0000 This work describes a large-scale parametric study conducted by PNNL using the previously developed and validated PWR finite element model, with the addition of a new generic BWR assembly model. The motivation for the parametric study was to characterize the broad range of SNF responses in the 30 cm package drop scenario. This was accomplished by varying the drop orientation, fuel assembly type (17 × 17 PWR and 10 × 10 BWR), burnup, cladding temperature, spacer grid buckling load, package mass, impact limiter stiffness, and mechanical gap conditions within the basket. A MATLAB framework was developed to automate LS-DYNA model generation and execution on PNNL institutional computing resources. In total, over 2000 simulations were performed. For each simulation, the SNF response was quantified in terms of permanent grid deformation, fuel rod contact pressure, and strains within the fuel rods, guide tubes, and water rods. The results provide valuable insight into the range of responses that could be reasonably expected from SNF in the 30 cm drop scenario, as well as the sensitivity to each input parameter. The results of this parametric study are a key component of the testing and modeling strategy the Spent Fuel and Waste Science and Technology program is using to close the external loads knowledge gap.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"170 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"116418364","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Earthquake NaTech Risk Assessment, Monitoring and Management of Cylindrical Liquid Storage Tanks With Floating Roof in Major-Hazard Industrial Plants","authors":"Michela Salimbeni, M. De Angelis, V. Vezzari, M. Ciucci","doi":"10.1115/pvp2022-84734","DOIUrl":"https://doi.org/10.1115/pvp2022-84734","url":null,"abstract":"\u0000 Earthquake is one of the natural events which is part of NaTech events (Natural Hazard Triggering Technological Disasters), due to interaction between natural and industrial risks. Industrial plants employ cylindrical liquid tanks with floating roof for storage of volatile and flammable products. Damages due to earthquakes affecting tanks with floating roof can cause major accidents involving dangerous substances, like hazardous releases, fires and explosions, especially due to the convective motion of the fluid caused by seismic excitation. The aim of this work is to inform about the most common damages in case of seismic event and to give some advice to seismic risk management through monitoring of critical elements of liquid storage tanks with floating roof. During an earthquake, damages to structural and non-structural elements can occur, and the non-structural elements are often the most involved in major accidents. In order to mitigate the consequences of a major accident, a monitoring system of the tank for management of the seismic risk can be installed, integrating new dedicated sensors into the existing monitoring network. The fiber optic sensors FBG (Fiber Bragg Grating) and FSI (Fiber Segment Interferometry) are a robust, multifunctional and removable alternative to the sensors already in use in the industrial field.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"237 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117020952","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Seismic Test Result (Static Load Test) of the Dynamic Functional Demand Valve for Nuclear Power Plant","authors":"Yoshinao Matsubara, Y. Tsutsumi, Urara Watanabe, Shota Tanemura, Y. Takemoto","doi":"10.1115/pvp2022-81652","DOIUrl":"https://doi.org/10.1115/pvp2022-81652","url":null,"abstract":"\u0000 The functional maintenance and confirmed acceleration of motor- and air-operated valves in nuclear power plants during an earthquake are regulated in the Japanese seismic design code (JEAC4601 (see Ref. [1])). In the present work, we used a resonant shaking table at the Central Research Institute of the Electric Power Industry (CRIEPI), which is capable of seismic tests at acceleration levels previously unachievable, in seismic tests carried out as high as 20 × 9.8 m/s2 (see Ref. [2] to Ref. [8]). On the other hand, JEAC4601 requires the structural evaluation for the seismic critical parts with allowable stress of 1.5-times yield strength (1.5Sy). In this study, in order to confirm the adequacy of the allowable stress, a static load test equivalent to 1.5Sy and more was conducted for the representative valves, namely, the air-operated globe valve and the air-operated butterfly valve. As a result, we confirmed that the required function of the valves was satisfied.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"44 6 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127125174","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Reheat Cracking of Low Alloy Steel During Fabrication and in Service in Oil and Gas Facilities","authors":"M. Dalal, J. Penso","doi":"10.1115/pvp2022-85406","DOIUrl":"https://doi.org/10.1115/pvp2022-85406","url":null,"abstract":"\u0000 Reheat Cracking is usually associated with the heat affected zone of restrained welded joints during either post weld heat treatment or elevated temperature service. Cracking is associated with the formation of fine intragranular precipitates. This precipitation strengthens the grain interiors and transfers the strain necessary for the relief of residual welding and system stresses to the grain boundaries. The overall effect is a reduction in creep ductility leading to intergranular failure in creep resistant steels. This mode of cracking poses a considerable practical problem particularly because the microstructural and compositional factors affecting its occurrence have not been clearly defined.\u0000 In this paper a literature review, case histories descriptions and research in progress are summarized.\u0000 The case histories include one overhead fluid catalytic cracking reactor overhead line during fabrication post weld heat treatment) and three high temperature high pressure steam piping after long and short term in service.\u0000 Research in progress includes the developing a testing procedure and the quantification of local strain level leading to stress relief cracking (SRC) during post weld heat treatment (PWHT) of welds in creep resistant steels. The testing approach involved implementation of a digital image correlation (DIC) technique with Gleeble-based SRC test.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123529405","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Coefficients of Friction in Dependence on Aging State of Elastomers – Experimental Identification and Numerical Simulation of the Experiment","authors":"M. Weber, M. Zaghdoudi, G. Brandt, A. Kömmling, M. Jaunich, D. Wolff","doi":"10.1115/pvp2022-84624","DOIUrl":"https://doi.org/10.1115/pvp2022-84624","url":null,"abstract":"\u0000 Elastomer seals are mounted as barrier seals in lid systems of containers designed for transport and disposal of negligible heat generating radioactive waste and as auxiliary seals in spent fuel storage and transportation casks (dual purpose casks (DPC)). When the behavior of mounted seals under normal and hypothetical accident conditions of disposal and transport is to be simulated, a comprehensive knowledge of their complex mechanical properties at every state of aging is necessary. In previous works, BAM’s efforts in experimental investigations on specimen artificially aged at different temperatures and times and the implementation of the found results in finite element material models were presented. Additionally, our approaches to reproduce the aging process itself and to extrapolate the results of artificially accelerated aging to longer times were presented. Numerical simulations have shown that the behavior of the seal during mounting and one-sided pressurizing and the resulting performance values such as leakage rate strongly depend on the coefficient of friction (COF) between flange and seal. The friction coefficient, in turn, depends on the aging state of the elastomer material as several publications suggest (see below).\u0000 Dynamic COF between an exemplary ethylene propylene diene rubber (EPDM) material and a stainless steel ball were determined by using a self-designed linear oscillation tribometer. Unaged and artificially aged EPDM specimen stored for 30 days and 100 days at a temperature of 150 °C were tested. A stainless steel ball (d = 10 mm) is brought in contact with the specimen’s surface und loaded by normal forces of 2.5 N, 5 N, 10 N and 20 N. During a reciprocating movement of the EPDM sheet, the horizontal force/friction force is continuously measured, and the COF can be derived.\u0000 It is well known that friction is a complex phenomenon especially in soft materials. It cannot be excluded that the measured friction force is influenced by additional force components, resulting from the ball’s grooving through the elastomer’s surface. This force depends on the penetration depth of the ball and on the resistance of the elastomer in its different states of aging. The latter results from microstructural changes i.e., chain scission and additional crosslinking that occur during aging which in turn influence the softening or hardening of the material.\u0000 A finite element (FE) ABAQUS® model was developed to reproduce the measurement process. It should help to better understand the physical mechanisms and to quantify the percentage of measured forces resulting from real friction on the one hand and forces resulting from unintended side effects that could falsify the result on the other hand. The behavior of the elastomer in its different states of aging is reproduced by a FE material model already presented in previous works of BAM.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"83 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132868785","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Reconstruction of Phased Array Ultrasonic Testing Image of Through Hole Based on Finite Element Analysis","authors":"Yingxu Feng, Haiqin Fang, Weican Guo, Di Jiao, Jianfeng Shi","doi":"10.1115/pvp2022-84468","DOIUrl":"https://doi.org/10.1115/pvp2022-84468","url":null,"abstract":"\u0000 As a most feasible defect detection method, phased array ultrasonic testing (PA-UT) plays an important role in nondestructive testing of pressure vessels and piping for its high detection efficiency. It’s necessary to obtain the size and position of defects or features for safety assessment to ensure the safe running of equipment if there is a defect. However, PA-UT suffers from image distortion due to acoustic attenuation and dispersion, as well as problems with imaging principle, which usually leads to errors when measuring the size and position of detected features. In this paper, the standard polyethylene block with a through hole was tested by PA-UT and the PA-UT images of artificial defects were obtained. At the same time, the PA-UT images were simulated by combining finite element analysis of the PA-UT process as well as the ultrasonic imaging algorithm. By comparing the test results and simulation results, the influence of sector scan angle and the number of elements in the active aperture on image distortion was analyzed. Moreover, based on the simulation method, the PA-UT images were post-processed to eliminate the distortion and reconstructed to be closer to the real size. This method could be further used for improving the imaging quality of the PA-UT testing system.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"55 2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"134515354","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding","authors":"Zenghu Han, M. Billone, Yung Y. Liu","doi":"10.1115/pvp2022-83911","DOIUrl":"https://doi.org/10.1115/pvp2022-83911","url":null,"abstract":"\u0000 The performance of used nuclear fuel (UNF) (i.e., cladding integrity, fuel retrievability, transportability, and cladding embrittlement) is considered important to the safety of both extended long-term dry storage and subsequent transportation for final disposition. Analytical analysis for UNF structural performance under storage and transportation conditions requires mechanical property data for the cladding materials (e.g., stress-strain relationships and failure limits). However, currently available mechanical properties and correlations are not sufficient because they are primarily based on uniaxial tension tests and pressurized-tube tests of cladding materials with only circumferential hydrides and are not suitable for cladding materials with radial hydrides. Ring compression testing (RCT) has become a very useful method for measuring the relative ductility of cladding and determining the ductility transition temperature of cladding materials. The results of RCT can be used to assess the mechanical behavior of cladding materials and determine the effects of burnup, hydride orientation, and temperature to support the development of the technical basis for extended storage and transportation of high-burnup fuel. Finite element analysis (FEA) has been used to characterize the stress state associated with RCT and to facilitate a better understanding of the deformation and the failure mechanisms of the cladding ring during RCT. Three-dimensional finite element (3D FE) models have been constructed using the commercial FE computer code ABAQUS™; the FE models include RCT machine stiffness, elastic and anisotropic plastic stress-strain properties, and large strain capability, and these models are used to simulate cladding rings subjected to RCT hoop-bending loading. Useful information regarding the material properties and behavior can be extracted by FE simulation of cladding RCT. In this paper, applications of FEA to RCT are described, and the limitations are also discussed.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"92 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130070640","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Real Time Mechanical Integrity for Pressure Vessels and Other Critical Assets","authors":"Simon Sierra, J. Wong, K. Dawson, Mateusz Podskarbi, D. Knezevic","doi":"10.1115/pvp2022-84348","DOIUrl":"https://doi.org/10.1115/pvp2022-84348","url":null,"abstract":"\u0000 There is a wall today in plant operations, maintenance, and reliability, where the integrity of assets is of critical importance to the health, safety, environmental and financial performance of plant operations. In many cases, the integrity of assets is only partially known, is informed by overly conservative assumptions or follows rules that have been established as part of historical approaches. The mechanical health of critical pressure vessels, piping and other assets is limited by the fidelity and model size of its finite element simulation. Operators must choose between speed, accuracy, and quality in setting up an asset health integrity system and legacy approaches provide partial answers at best and/or workflows that are not well suited for asset health integrity systems.\u0000 Industry has relied on finite element analysis to determine structural integrity during design, but new advances in numerical reduction methods and computational advances have been combined to dramatically decrease the time needed to solve high fidelity whole-asset structural simulations to visualize stress fields, accumulated fatigue life, and other structural/mechanical analysis in real-time.\u0000 This paper will address this problem through the lens of two real-world pressure vessels, demonstrate the limitations of legacy approaches, and discuss the benefits of running structural simulations in real time.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"25 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127749999","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}