Mahsa Mehranfar, Juan Mejia, S. Hassanien, James Martin
{"title":"Integrity Mitigation Prioritization Using Multi-Criteria Decision-Making","authors":"Mahsa Mehranfar, Juan Mejia, S. Hassanien, James Martin","doi":"10.1115/pvp2019-93621","DOIUrl":"https://doi.org/10.1115/pvp2019-93621","url":null,"abstract":"\u0000 In-line Inspection (ILI) tools are regularly used for inspecting transmission pipelines. However, it is challenging to use such technology for a large portion of pipes; e.g. terminals and pumping stations, because of diameter changes, tight turns, or other pipe/inspection characteristics. Non-contact pipeline magnetic testing (NPMT) is a well-suited technique to inspect potentially non-ILI pipes. This paper presents a new framework for selecting and prioritizing digs-based LSM high severity features. A multi-criteria decision-making approach was developed using pair-wise comparisons which stems from the Analytical Hierarchy Process (AHP). AHP is a structured technique for organizing and analyzing complex decisions to help the decision maker set priorities and make the best decision given available information. In addition to the application of AHP, a cost benefit analysis and evaluation of risk have been conducted in order to support a risk-informed decision-making for selecting the top priority digs. Pipe properties, LSM tool reported data and Subject Matter Expert (SME) opinion were utilized in order to efficiently render a decision regarding prioritization of dig sites.\u0000 The developed approach can be used as a regular process to prioritize similar dig programs. This method is capable of ranking different dig sites based on SME opinion as well as construction information and LSM reported data.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"111 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133879563","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}
Liu Xiaoliang, Xuedong Chen, Z. Fan, Hui-Ming Jiang
{"title":"Preparation and Properties of Au/SnO2 Thermocouples for Material Testing Apparatus of Pressure Equipment","authors":"Liu Xiaoliang, Xuedong Chen, Z. Fan, Hui-Ming Jiang","doi":"10.1115/pvp2019-93346","DOIUrl":"https://doi.org/10.1115/pvp2019-93346","url":null,"abstract":"\u0000 Thermocouples are the most common temperature measuring components in petrochemical, metallurgical, aerospace and other fields. However, due to the influence of working environment and its own structural characteristics, the thermocouple is highly susceptible to electromagnetic interference in the environment during its work, which seriously affects its temperature measurement accuracy. In this paper, three different shapes of Au/SnO2 thermocouples were prepared by screen printing technology, and their microstructure, thermoelectric properties and anti-electromagnetic interference were studied. The results show that the Au/SnO2 thermocouples with different shapes can crystallize well after sintering at 750 °C and above. When temperature difference is from 50 to 300 °C, thermocouples with different shapes can produce stable thermoelectric potential, and the shape has no effect on the output thermoelectric potential. The Au/SnO2 thermocouple after 850 °C sintering has the best thermoelectric performance. Au/SnO2 thermocouples can work normally in electromagnetic fields of 3 V/m or less, while standard PtRh10-Pt thermocouples can not work normally in electromagnetic field of 3 V/m. The Au/SnO2 thermocouple obtained in this study has the advantages of simple preparation method, small size, stable output thermoelectric potential and strong anti-electromagnetic interference ability.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129044998","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":"International Civil Ageing Management and Assessment Methodology of Concrete","authors":"F. Wilde, C. Bont","doi":"10.1115/pvp2019-93029","DOIUrl":"https://doi.org/10.1115/pvp2019-93029","url":null,"abstract":"\u0000 For many nuclear power plants worldwide the operation period will be extended to 60 or 80 years in the coming years. As the operation period increases, the importance of knowledge of ageing mechanisms increases. In the framework of LTO there is limited knowledge about ageing and structural integrity of concrete structures.\u0000 Knowledge about the strength of concrete structures and modelling thereof can be improved for a more complete knowledge base on ageing and degradation mechanism in nuclear facilities. Therefore, effort is required to improve the knowledge of concrete, material models and finite element modelling techniques as well as the assessment method.\u0000 Recent developments have shown that ageing of civil structures receive more attention internationally (E.g. concrete degradation in bunker building Doel). Traditionally a large part of the research and development is focused on mechanical issues like piping and vessels. In order to increase the knowledge in the field of civil structures, the focus is on investigation of ageing of concrete and determining analysis methods.\u0000 This paper focuses on the development of a practical assessment method for ageing of civil structures.\u0000 As a first step information from international publications and other sources on civil structures ageing issues and management thereof, will be gathered. Well known international standards taking care of ageing phenomena based on problem areas and good practices are IGALL and GALL.\u0000 IGALL and GALL contain information tables based on international experience. This is the starting point of the research in finding an assessment methodology for civil ageing management. It will be shown that IGALL and GALL contain very similar elements. Sorting on the AMPs results in a practical set of datasheets with summarizing information per AMP, including the underlying international experience. The datasheets are of limited size, presenting an helpful overview of the relevant structures or components, materials, environment and mechanisms.\u0000 A method for civil ageing management is proposed which will be applied and developed in more detail in future research. Further research is necessary to develop a specific assessment methodology for concrete.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"50 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115534270","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":"SR-102 Package Replacement","authors":"Christopher P. Cable","doi":"10.1115/pvp2019-94068","DOIUrl":"https://doi.org/10.1115/pvp2019-94068","url":null,"abstract":"\u0000 The SR-101 Reservoir Package was placed into service in the early 1990s to ship various configurations of pressurized gas bottles. The SR-101 replacement, the SR-102, is a performance based Department of Transportation (DOT) package designed for shipping currently authorized compressed gases. This paper presents the design, fabrication, and testing processes used to produce the requisite Safety Analysis Report (SAR) that will provide the basis for package certification.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"33 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129404171","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":"Continued Safe Operation (LTO Research Reactors) High Flux Reactor, Petten","authors":"L. Stefanini, F. Wilde, J. Offerein","doi":"10.1115/pvp2019-93030","DOIUrl":"https://doi.org/10.1115/pvp2019-93030","url":null,"abstract":"\u0000 The HFR is one of the most powerful and versatile Research Reactors in the world. Because of its strategical importance in the medical isotopes production, after 57 years of operating experience a Continued Safe Operations (CSO) mission will take place. The CSO project structure is based on the outline given in the IAEA draft Safety Guide SSG-48. The ageing management for the HFR is evaluated based on the IAEA Specific Safety Guide SSG-10. Moreover, the approach to the contents of the project is supported by the IAEA Draft Guidelines for Peer Review of “Ageing Management of Research Reactors for Continued Safe Operations”. The HFR is the second Research Reactor (RR) in the world to undergo this type of assessment and its experience will be extremely valuable in setting the international standards for CSO of research reactors. This paper describes the phases of the CSO project, the challenges encountered and the experience built during its development.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121659143","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":"Safety and Risk Management Analysis of Accidents Related to Pressure Vessels and Piping in Alberta Petrochemical Industry From 2008 to 2017","authors":"Mohamed Esouilem, A. Bouzid, S. Nadeau","doi":"10.1115/pvp2019-93010","DOIUrl":"https://doi.org/10.1115/pvp2019-93010","url":null,"abstract":"\u0000 In recent decades, many accidents involving pressure vessels and piping components (PVP) have occurred in North-America. Several studies have been conducted to understand their causes and find suitable solutions to reduce their frequency. Most of the researches have focused on the technical causes of these accidents and the subsequent implementation of safety management strategies. These researches highlight that the main technical causes are leak and rupture. From this standpoint, it is important to deepen the study of leaks and ruptures accidents. In Alberta alone, the Alberta Energy Regulator (AER) demonstrated that more than 15 root causes initiated leak and rupture failures in PVP since 1990.\u0000 This paper presents an analysis of the frequency of accidents, their severity, their causes and the risk associated in the Alberta petrochemical industry from 2008 to 2017. This study proposes an exponential decay to estimate the frequency of accidents involving PVP and identifies the most important causes based on a severity analysis. The results based on the developed model show that there is a good agreement between the predicted and observed accidents frequency from 2008 to 2017. The severity analysis results show that the main factors contributing to accidents are corrosion, construction deficiency and overpressure. Finally, the proposed model of frequency and severity of observed and predicted PVP failures needs improvements to better predict the risks and be useful for prevention.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127282965","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}
Y. Ishizaki, Futoshi Yonekawa, Teppei Suzuki, A. Hase
{"title":"Flange Neck Creep Damage Below API 579-1/ASME FFS-1 Creep Damage Threshold Triggered by Ring Joint Dissimilar Flanges","authors":"Y. Ishizaki, Futoshi Yonekawa, Teppei Suzuki, A. Hase","doi":"10.1115/pvp2019-93034","DOIUrl":"https://doi.org/10.1115/pvp2019-93034","url":null,"abstract":"\u0000 Reduced flange design is commonly used for fixed bed reactor top nozzles due to the easier provision of manway access for down time maintenance. In this design, a dissimilar flange design is often opted for a material break point of the unit to avoid a dissimilar weld in the piping system.\u0000 This design concept is also adopted our fixed bed reactors. The vessel is made of 2.25Cr steel including 40inch top nozzle. On the 2.25Cr top nozzle, 347SS dissimilar reduced flange was provided for manway access purpose in conjunction with top nozzle. It had been operated for 54,000Hrs until the reduced flange neck experienced minor cracks. As the total operating hours reached 140,000Hrs, cracks were propagated and leaked. According to their inspection record of those cracks, a creep damage like pattern was observed while its operating temperature was 520Deg. C, that was below the 550Deg.C of ASME Sec II Part D[1] allowable stress table time dependent allowable stress range, and also below the 537Deg.C of potential creep damage threshold indicated in API 579-1 / ASME FFS-1[2] Table 4.1 which is the same with API 571 Table 4.3[3]. As we conducted FEM analysis using an isochronous curve based on API 579/ASME FFS-1 Omega Method[2], the results well explained the actual damage and life, and confirmed a creep damage could happen below the creep damage threshold of API 579-1 / ASME FFS-1[2] and API 571[3], depending on the multiaxial stress state.\u0000 In this paper, the detail of the inspection findings and isochronous model FEM analysis including remaining life assessment as well as comparison between the damage and analysis will be discussed.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"9 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122675440","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":"Valve Modeling Methods for Modal Analysis","authors":"Ronald S. Farrell, L. I. Ezekoye","doi":"10.1115/pvp2019-93904","DOIUrl":"https://doi.org/10.1115/pvp2019-93904","url":null,"abstract":"\u0000 This paper presents several modeling methods for performing a valve assembly modal analysis. It discusses the background of the methods, their strengths and limitations, and then introduces a new approach that can be used in performing valve modal analysis. An early paper presents a classical approach based on a lumped mass model and the Rayleigh energy principal to determine primary mode natural frequencies. A follow up paper reaffirms the classical method and introduces enhancements. A recent paper provides a comparative study of the classical approach, laboratory testing, and solid modeling results using the finite element analysis program ANSYS Mechanical. In this paper, a third approach is presented, which is an extension of the classical method, where 3-D beam-based geometry is defined using the ANSYS SpaceClaim program that is then ported to ANSYS Mechanical. The classical and solid modeling approaches from the previously cited papers are reviewed to highlight the modeling evolution and then the newly developed approach is presented. An example is presented that compares natural frequency results of the new method and the previous methods.\u0000 The motivation for the new method is to provide better compatibility with 3-D piping system models, which are typically used to study the effect of valve mass and stiffness on system response without the complexity of a solid model or the difficulty of communicating the details of a classical model to the system modeler.\u0000 Much of the process of creating a 3-D beam model is automated. It uses input from an existing classical model and employs the following ANSYS software packages: SpaceClaim, Workbench, Mechanical, and ACT. A great feature of the resulting 3-D model is that beam geometry is more realistic to scale, and therefore provides valuable user feedback for checking model validity. This approach is an improvement over the classical model where only manual data input validation is possible. Other benefits of the new method are covered in greater detail in the paper.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"13 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"117173922","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}
S. Das, Suranjan Sarkar, Gary H. Lee, Ong Junxiong
{"title":"Prediction of Flow-Accelerated Corrosion/Erosion in High-Speed Ejectors Using a CFD Model","authors":"S. Das, Suranjan Sarkar, Gary H. Lee, Ong Junxiong","doi":"10.1115/pvp2019-93668","DOIUrl":"https://doi.org/10.1115/pvp2019-93668","url":null,"abstract":"\u0000 In high-velocity ejector systems containing liquid droplets, ejector walls are sometimes damaged by flow-accelerated corrosion/erosion. Velocity, droplet size, impact angle etc. are the most important parameters affecting flow-accelerated (FA) corrosion/erosion. In our plant operation, we had experienced FA corrosion/erosion and consequent failure even with very low impact angle. To understand the leak/ failure, we have adopted the Euler-Euler multiphase model-based CFD approach. In the Euler-Euler multiphase model, the liquid droplets are modelled as dispersed phase while the gas-steam is modelled as a continuous phase. To capture the droplet dynamics very accurately, appropriate correlations for drag, lift and wall lubrication force have been chosen. In CFD simulations we have observed liquid film formation at the ejector wall. The liquid film moves along the ejector wall creates a very high wall shear-stress. In the location of high wall shear-stress, one can expect high FA corrosion/erosion and consequent leak. Qualitative comparison of the X-ray image of the actual equipment with the CFD results for wall-shear stress shows very good agreement in terms of predicting leak location. Moreover, we have varied the droplet size and the liquid fraction in the upstream of the ejector. Qualitatively we have observed that with increase in droplet size the material removal rate increases, however, the affected area of the leak decreases. The more liquid in the system increases the wall-shear stress very rapidly. The present CFD model is useful for predicting the leak-prone location and taking predictive actions (e.g. cladding the wall with a high-grade material).","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"12 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125727463","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}
Charles Le Nevé, Sophie Loyan, L. Jeune, S. Mahaut, Serge Demonte, D. Chauveau, Romain Renaud, M. Tessier, Nicolas Nourrit, Anthony Le Guellaut
{"title":"High Temperature Hydrogen Attack: New NDE Advanced Capabilities — Development and Feedback","authors":"Charles Le Nevé, Sophie Loyan, L. Jeune, S. Mahaut, Serge Demonte, D. Chauveau, Romain Renaud, M. Tessier, Nicolas Nourrit, Anthony Le Guellaut","doi":"10.1115/pvp2019-94001","DOIUrl":"https://doi.org/10.1115/pvp2019-94001","url":null,"abstract":"\u0000 In petroleum industry, hydrogen is used in many assets. With temperature and pressure, hydrogen can damage materials. This damage is called High Temperature Hydrogen Attack (HTHA) and is a time dependent degradation mechanism that can affect the integrity of steels used for pressure containment operating above about 400°F (204°C). HTHA has caused major accidents in Petroleum Industry.\u0000 API RP 941 [1] currently provides guidance for steel selection (and so susceptibility to attack) in relation to temperature and ppH2 via Nelson curves. In the last edition, 4 stages of degradation for both base metal and weld metal are described.\u0000 In the past, only stage III was detectable by the combination of different Ultrasonic methods which were known as AUBT – Advanced Ultrasonic Backscatter Technique. But, capability of detection was limited to defects above 500–1000μm, correspondent to small fissures. So, it was impossible to detect early stage of degradation as steel grain size (around 50μm).\u0000 For several years, performances of non-destructive techniques have rapidly increased and new advanced ultrasonic technologies are available such as:\u0000 - Phased Array Ultrasonic Techniques (PAUT)\u0000 - Time Of Flight Diffraction (TOFD)\u0000 - Total Focusing Method (TFM)\u0000 This paper describes latest techniques and results obtained by Total and French Welding Institute in laboratory, and discuss the efficiency of the methods, over real HTHA degradation blocks. An overview of TFM is also proposed by CEA who work on innovating development to increase the performance of this technique.","PeriodicalId":339189,"journal":{"name":"Volume 7: Operations, Applications, and Components","volume":"30 7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126082712","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}