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

{"title":"Study on Ultrasonic Phased Array Imaging Technique for Direct Contact Inspection on Double Curved Surface","authors":"Jingwei Cheng, Z. Fan, X. Chen, Yangguang Bu, Haibin Wang, Zhe Wang","doi":"10.1115/pvp2022-84678","DOIUrl":"https://doi.org/10.1115/pvp2022-84678","url":null,"abstract":"\u0000 Ultrasonic testing technique is commonly used for nondestructive inspection of pressure vessels and pipelines. Normally, ultrasonic phased array system can effectively and efficiently image different types of defects within the structures through direct contact method. However, the double curved geometries of inspection targets (e.g. pipe elbows, pipe weld joints and turbine blades) give rise to challenges in direct contact between probe and surface. Therefore, based on the full matrix capture and total focusing method (TFM), this paper uses a conventional phased array transducer with flexible wedge to detect and image a double curved sample with different depths of side drilled holes. The test specimen is fabricated in a ring shape with an outer diameter of 150 mm, an inner diameter of 100 mm and a 2 mm high weld reinforcement. It is found that the full matrix data can be captured to image the structure interior by either extracting the surface profile or directly imaging with preset surface dimensions. The proposed technique has also demonstrated its capability on realizing high-resolution imaging of 1 mm side drilled holes at different depths. Our promising results show that the method has the ability to reliably locate and quantitatively evaluate the defects with complexly shaped structure.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"149 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":"122133633","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":"New Evaluation Method for Seismic Fatigue Damage of Plant Pipeline (Quantitative Performance and Consideration of Application)","authors":"F. Inada, M. Sakai, R. Morita, I. Tamura","doi":"10.1115/pvp2022-84154","DOIUrl":"https://doi.org/10.1115/pvp2022-84154","url":null,"abstract":"\u0000 In previous reports, it was shown that the cumulative absolute velocity (CAV) for each wave of the pipe seismic response corresponds to the vibration stress amplitude. A new seismic fatigue evaluation method was proposed by applying this relationship to Miner’s law of material fatigue damage. As a result, the cumulative fatigue damage can be calculated in proportion to the CAV of each wave to the power of 2.4. In this study, how the new method can be used to evaluate the cumulative fatigue damage quantitatively is considered. The cumulative fatigue damage was evaluated by the rain flow method as well as the new method where the parameters showing the effect of the concentrated mass and the pipe configuration on the vibration stress-velocity relationship were calculated accurately using the precisely analyzed mode function. The two results were found to be in good agreement. It is considered that this new method can give the evaluation result that envelops the pipes of the entire plant by appropriately setting the parameters.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"337 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":"123060769","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":"Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems","authors":"S. Suffield, P. Jensen, W. Perkins, B. Jensen, Christopher L. Grant, Casey Spitz","doi":"10.1115/pvp2022-83982","DOIUrl":"https://doi.org/10.1115/pvp2022-83982","url":null,"abstract":"\u0000 Deposition models were built to evaluate contaminant deposition on spent nuclear fuel (SNF) canisters. The primary contaminant of concern is chloride, which is dispersed in the atmosphere and then deposits onto the canisters. During dry storage, the primary degradation process is likely to be Chloride Induced Stress Corrosion Cracking (CISCC) at the heat-affected zones of the canister welds. It is known that stainless steel canisters are susceptible to CISCC; however, the rate of chloride deposition onto the canisters is poorly known, based on sparse field data from a small number of sites. The models presented in this study could be useful for determining the rate of deposition on the canisters and the likelihood of CISCC to help with SNF canister ageing management.\u0000 The deposition models were developed with the commercial computational fluid dynamics (CFD) code STAR-CCM+. Various deposition mechanisms were considered and incorporated into the models, and a sensitivity study was conducted to determine the most important mechanisms for deposition within a SNF storage system. The models included both a vertical and horizontal configuration storage system: NAC International’s Modular, Advanced Generation, Nuclear All-purpose STORage System (MAGNASTOR®) and a NUHOMS® horizontal storage module respectively. The resulting canister deposition on the horizontal canister is visually compared with inspection data taken onsite at the Calvert Cliffs Nuclear Power Plant. These models are preliminary, and development of the models will continue. Future validation exercises are currently being planned, including the Canister Deposition Field Demonstration (CDFD) effort funded by U.S. Department of Energy Office of Nuclear Energy Office of Spent Fuel and Waste Science and Technology. The goal of the modeling presented is to demonstrate a potential modeling technique that could be used to plan and inform SNF canister ageing management programs with predictive models for the timing and occurrence of canister CISCC.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"7 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":"131531240","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":"Analysis of Mainframe Computer Structures Using Implicit and Explicit Finite Element Analysis","authors":"B. Notohardjono, S. Canfield, Suraush Q. Khambati, R. Ecker","doi":"10.1115/pvp2022-84831","DOIUrl":"https://doi.org/10.1115/pvp2022-84831","url":null,"abstract":"\u0000 This paper discusses the finite element analysis (FEA) methods used to analyze the performance of a mainframe computer’s structural frame under a standard seismic loading such as that defined by Telcordia NEBS Zone 4. Specialists in the earthquake robustness area need to consider the basic mainframe structural information such as the total mass and the center of gravity in order to properly size and install tiedowns to prevent tiedown failure which can lead to hazardous tip-over events. To ensure successful operation through a seismic event, the total deflection of the top of the mainframe is a good indicator of ensuring the mainframe computer’s continuous operation.\u0000 As the mainframe computer’s total weight and the center of gravity varies depending on the specific customer configuration, this paper will examine the two extreme end cases: the lowest mass configuration with the highest location of the center of gravity and the highest mass configuration with the highest center of mass location. From a structural perspective, the higher the initial resonance frequencies, the more rigid the structure and the smaller the upper frame deflection will be. Thus, given a mainframe structure, the finite element analysis results will provide information on the weakest direction resonance frequency, which is in the narrow, side-to-side direction, along with the mainframe rack tiedown loads and maximum top frame deflection.\u0000 Given a mainframe structure’s finite element model and standard time domain seismic acceleration input at the base of the frame structure, the explicit finite element method will provide the performance of the structure namely the first resonance frequency, the maximum stresses at the rack structure, load at the tie down locations and the maximum top frame deflection. The explicit finite element analysis model can take into account the non-linear contact regions around weld areas and between adjacent sheet metal frame components as well as material non-linearities. The result of the FEA analysis of the several mainframe configurations will be compared to the results from actual seismic earthquake mainframe tests.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"48 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":"133646748","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":"Rocking Response Analysis of Flat-Bottom Cylindrical Tanks Considering Rotational Inertia of Content Liquid","authors":"Y. Yoshida, T. Taniguchi, T. Nakashima","doi":"10.1115/pvp2022-84909","DOIUrl":"https://doi.org/10.1115/pvp2022-84909","url":null,"abstract":"\u0000 This paper proposes an analytical method for calculating rocking responses of unanchored tanks during seismic ground motion. Some researchers have proposed the analytical methods to calculate seismic responses of unanchored tanks without considering the rotational inertia of content liquid. In other words, most of method for a time-history analysis of tank rocking responses are assumed that an equilibrium equation in direction of rotation can be formulated as a static equilibrium equation in which the overturning moment and the restoring moment are equal. Even a model that considers rotational inertia of content liquid was proposed in the past, the definition of moment of inertia is ambiguous. On the other hand, there a study that derives moment of inertia from a physical background and alleges the importance of the moment of inertia in the tank rocking response.\u0000 In this study, an analytical method of a time history analysis of tank rocking motion considering the rotational inertia of content liquid is proposed. Furthermore, results of the proposed method are compared with results of the FEM dynamic analysis to validate the accuracy of the proposed method. Finally, comparisons with results of the conventional calculation method are also conducted.","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":"133976028","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":"Regulatory Testing and 3D Scanning Methodology of the DPP-1 Type Shipping Container for NCT and HAC Tests","authors":"Oscar Martinez, Abiodun Adeniyi, Paul S Nogradi, B.W. Van Hoy","doi":"10.1115/pvp2022-86807","DOIUrl":"https://doi.org/10.1115/pvp2022-86807","url":null,"abstract":"\u0000 The safe transportation of radioactive material using appropriately designed and certified transportation packages is important for protecting the public and environment. In the United States, the US Department of Transportation (DOT) regulates all transportation of radioactive material with input from the US Nuclear Regulatory Commission. All packages that contain radioactive materials must be transported and regulated by the requirements set by the DOT Class 7 transportation of hazardous material. Federal regulations place strict administrative controls on the transport of radioactive materials. The two main goals for transporting radioactive materials are that (1) safety is primarily focused on the package because it is the first line of defense and (2) package integrity is directly related to the degree of the hazard of the radioactive material contents. The two-part goal ensures that the correct package is used. Type B packages are designed to transport radioactive materials with the highest level of radioactivity. Examples of material transported in Type B packaging include spent nuclear fuel, high-level radioactive waste, and high concentrations of other radioactive materials. The purpose of this test protocol was to determine the effects of structural and thermal testing on package performance in a Type B shipping package, Defense Program Package-1 (DPP-1).","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"19 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":"124978849","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":"Classification Recognition of Long Distance Oil and Gas Pipeline Girth Welds MFL Signal Diagrams Based on VGG16 Network","authors":"Liyuan Geng, Shaohua Dong, Li Zheng, Shengwei Li","doi":"10.1115/pvp2022-79842","DOIUrl":"https://doi.org/10.1115/pvp2022-79842","url":null,"abstract":"\u0000 In recent years, with the development of long-distance oil and gas pipelines, the number of accidents, most of which caused serious consequences, is increasing gradually. According to statistics, pipeline cracking caused by girth weld problems accounts for a large proportion of all. Girth weld defects of long-distance oil and gas pipelines, such as cracks, incomplete fusion and incomplete penetration, seriously threaten the safety of pipelines. Because the internal magnetic flux leakage detection (MFL) signal is complex at the girth weld, it is difficult to judge the defect type through conventional data analysis. In this paper, MFL signal screenshots of girth welds, which are automatically captured from MFL client software by the Python program, are the training sample set of VGG16. This training sample set which includes 1396 samples labeled with radiographic test results after girth welds excavation, is divided into three categories: qualified samples, unqualified samples with circular/strip defects, and unqualified sample with crack/incomplete fusion/incomplete penetration defects. The deep learning network after training is used to predict the classification of 156 test samples, and the prediction accuracy is 78%. This method can effectively judge whether there are hazardous girth weld defects types, which are significant for safety management of long-distance oil and gas pipeline girth welds.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"56 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":"132561573","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":"Stress Analyses of Large Unanchored Open-Topped Oil Storage Tanks With Tapered Shells","authors":"Lei Shi, Yatong Zhao, Zijian Huang","doi":"10.1115/pvp2022-83656","DOIUrl":"https://doi.org/10.1115/pvp2022-83656","url":null,"abstract":"\u0000 The aim of the present paper is a deep experimental and numerical investigation of stress for large-scale oil tanks with a floating roof. Field stress testing of open-topped oil storage tanks with a capacity of 100,000 m3 was performed during the hydrostatic testing by resistance strain gauge technology to investigate the stress levels and distribution of tank bottom and shell. Large amounts of data in this testing that are valid and reliable by adopting various measures have been collected and the stress levels and distributions of tank shell and bottom which provide valuable material for the safety assessment of oil tank operation have been surveyed. Meanwhile, a new 3-D finite element model is developed to simulate stresses in the tank. By comparing the calculated results with the experimental data, the validity of the developed finite element model is verified. Both experimental and numerical results show that the tank bottom shows mainly the radial bending stress at the maximum liquid level. The tank shell at the base shows mainly the radial bending stress however tank shell occurs swelling deformation with the increasing of the height of gauge point, the circumferential membrane stress is the main component. The results suggest that the stress of the fillet joint is relatively high in the tank which will be helpful in improving the design of large-scale oil tanks and assessing the structural integrity.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"373 7","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-07-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"120890928","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":"The Study of Impact Damage of Carbon Fiber Wrapped Cylinder With Aluminum Liner Based on X-Ray Digital Radiography","authors":"S. Chai, Liang Huang, Huai-Bei Dai, K. Bo, Xiang Li, G. Deng, Qianghua Huang","doi":"10.1115/pvp2022-84458","DOIUrl":"https://doi.org/10.1115/pvp2022-84458","url":null,"abstract":"\u0000 With the development of hydrogen fuel cell vehicles, Carbon Fiber Wrapped Cylinder with Aluminum Liner are widely used in the field of the on-board storage of compressed hydrogen. Impact damages are common in Carbon Fiber Wrapped Cylinder with Aluminum Liner because the composite laminate structure is sensitive to impact load. In this work, the DR method with the technology of compensation block is used to detect impact damage of Carbon Fiber Wrapped Cylinder with Aluminum Liner, and analyzes the expansion of impact damage after different number of pressure cycles. The main damage of Carbon Fiber Wrapped Cylinder with Aluminum Liner caused by impact are delamination of carbon fiber overwrap, debonding between cylinder liner and carbon fiber overwrap, and bulge inward of aluminum liner, and these damages become more serious as the impact energy increases from 500 J to 1500 J. As the pressure cycle test is performed to the Carbon Fiber Wrapped Cylinder with Aluminum Liner, the impact has a serious effect on the fatigue performance of the cylinder. In addition, the debonding between the cylinder liner and the carbon fiber overwrap and the bulge inward degree of the aluminum liner are reduced due to the internal pressure. When the impact energy is low (i.e., 500 J), the pressure cycle has no significant influence on the delamination defect of carbon fiber overwrap. Besides, under the high impact energy conditions (i.e., 1000 J and 1500 J), the delamination defect of the overwrap in the impact center appears obvious expansion with the pressure cycle, while the delamination defect at the impact edge does not propagate obviously.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"109 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":"116149539","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 and Seismic Response Analysis of U-Shaped Tube Bundle With Triangular Arrays in Steam Generator","authors":"K. Hirota, M. Monde, Naoki Ono, Tomohito Nakamori, Masahito Matsubara, T. Mineno, Koshi Taguchi","doi":"10.1115/pvp2022-83643","DOIUrl":"https://doi.org/10.1115/pvp2022-83643","url":null,"abstract":"\u0000 Ensuring a complete integrity of steam generators’ tubes during earthquakes is critical. So far, excitation tests have been conducted for various square array tube bundles in order to grasp vibration behavior during seismic excitation. A seismic analysis method using a simple model has been developed and subsequently verified by comparing the results against those of the above mentioned tests.\u0000 In this study, seismic excitation tests were carried out for a U-shaped tube bundle with a triangular close-packed array using a full-scale test specimen as the triangular tube array with thinner anti-vibration bars (AVBs) has different vibration characteristics compared with a squared array one.\u0000 Natural frequencies, modes and stress distribution in the tube bundle, obtained during the experiment, were applied in order to verify the seismic analysis method through the use of a linear analysis model with all tubes and AVBs connected to each other by linear springs as well as with a nonlinear analysis model with gap elements to simulate contact and sliding between all tubes and AVBs.\u0000 The vibration displacement of the top of the tube bundle calculated by the linear model were in good agreement with the test result. Stress distribution in the tube array calculated using the nonlinear model were in good agreement with the test result. It has been concluded that the linear and nonlinear analysis models are applicable to seismic analysis including for the case of a U-shaped triangular tube array in a steam generator.","PeriodicalId":111167,"journal":{"name":"Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division","volume":"1 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":"127315566","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}