bluuebunny/crossref_metadata_2025_split huggingface dataset:
Shake Table Testing for a Multi-Component Prototype Industrial Plant: Input and System Modelling Issues
Authors: Nardin Chiara , Bursi Oreste S. , Paolacci Fabrizio , Quinci Gianluca , Lanese Igor , Pavese Alberto 
Published: October 2021

Abstract
Recent destructive earthquakes in China (Sichuan, 2008 and Yushu, 2010), Japan (Tohoku, 2011) and Italy (Emilia, 2012) highlighted the social and the political consequences of seismic risk due especially to industrial facilities. More precisely, critical interactions between the supporting structure and process components reveal to be extremely vulnerable in a seismic scenario and capable to lead serious damage of process equipment and potential release of hazardous substances. This latter circumstance, underestimated by current codes, in addition to loss of production, pose a serious danger to humans and the surrounding environment. Based on these premises, the SPIF project — Seismic Performance of Multi-Component Systems in Special Risk Industrial Facilities — was proposed within the framework of the European H2020 - SERA funding scheme. In greater detail, the goal of the project is the investigation of both the seismic behavior and the dynamic interactions of a representative industrial substructure equipped with complex process technology by means of shaking table tests. A full-scale mock-up composed by two single-bay moment resisting frames with three floors equipped with tanks, flanges, pipes, cabinet etc. was built and tested using a unidirectional shaking table activated with several earthquake levels. More precisely, the salient features investigated by shaking table testing are: i) the interaction between a primary moment resisting frame steel structure and secondary process components that influence the performance of the whole system; ii) input and system modelling capable to faithfully reproduce the seismic response of SPIF tested structure. The comprehensive testing campaign demonstrated a clear dynamic interaction between the primary steel structure and secondary process units that emphasizes the need of further investigations and studies.
Acceleration and Displacement Response of Base Isolation System With Friction Subjected to Random Vibration
Authors: Aoki Shigeru , Kurita Katsumi 
Published: October 2021

Abstract
Various types of devices have been developed to reduce seismic response of the mechanical systems. Base isolation system is one of them. In such devices, friction characteristic is used. The authors have developed a base isolation system with friction for relatively small mechanical system. In ordinary case, response of mechanical system decreases with the increase of friction coefficient. However, in the experiment to examine the effectiveness of base isolation system, it is found that acceleration response takes minimum value at some friction coefficient. In this paper, experimental results are examined using a simplified model. As earthquake excitations, some types of random vibration are used. Responses of the mechanical system are obtained from moment equations using the equivalent linearization method. It is demonstrated that acceleration response takes minimum value at some friction coefficient in some conditions.
High Temperature Aged Leakage Relaxation Screening Tests on Confined Flexible Graphite Gaskets
Authors: Bouzid Abdel-Hakim , Das Shubhra Kanti 
Published: October 2021

Abstract
Flexible graphite-based gaskets are used extensively in high-temperature applications as a replacement of asbestos based gaskets. The effect of aging and temperature exposure of flexible graphite sheet gaskets was the subject of a previous work [1,2], however, the effect when flexible graphite is in a confined gasket configuration is not known.
This study outlines the performance evaluation of the elevated temperature behavior of flexible graphite-based gaskets under a confined configuration and exposed over a long period employing HALR (High temperature Aged Leakage Relaxation) fixture. This ARLA-like fixture can retain the mechanical feature of the ATRS/HATR while allowing the cold leakage rate and weight loss measurement. Four different confined gasket configurations, namely corrugated metal, spiral wound, kammprofile and double jacketed, are evaluated within a temperature range of (427 to 649 °C) 800 to 1200 °F and exposure time of 2500 hours. Graphite weight loss, gasket thickness change, leakage and tightness parameter, creep and relaxation measurements were taken at regular intervals for each gasket style. To better understand the aging process, these critical mechanical and leakage properties are scrutinized; the degradation process related to mainly graphite oxidation is further discussed, and a conclusion is drawn.
Assessment of Dynamic High Momentum Slug Loads on Piping Following STHE Tube Rupture
Authors: Weyer Robert 
Published: October 2021

Abstract
Transient fluid loads in process piping have gained renewed focus recently with the design and construction of many LNG plants. The case of the shockwave (waterhammer) in piping following the rupture of a tube in a STHE has been well studied. Less attention has been paid to the high momentum slug flow which can occur when liquid slugs are accelerated in the piping by the gas.
This paper will examine some of the practical considerations for assessing the dynamic loads resulting from this high momentum slug flow. A method to obtain the force vector for any 3-dimensional change in direction will be presented. The use of DLFs for loads where a detailed time history profile is available will be discussed. The possibility of taking credit for simultaneously acting forces will be investigated.
The applicability of the B31.3 allowable stress for occasional loads will be examined and compared against advanced finite element models using shell elements.
Design Considerations for Half-Pipe Jackets Operating Under Vacuum Conditions
Authors: Mathkar Ameya , Gopalakrishnan Shyam , Pathre Sujay S. 
Published: October 2021

Abstract
Pressure vessel is defined as an equipment having pressure differential between inside and outside. The pressure is accompanied with suitable temperature of the fluid. Based on the process requirement, the temperature within the pressure vessel is maintained. The temperature can be controlled by application of heat from direct or indirect source. Half-pipe jacket or limpet coil is one of the methods to maintain the temperature of fluid in the pressure vessel. The nonmandatory Appendix EE of ASME Sec. VIII, Div. 1 and Para. 4.11.6 of Part 4 of ASME Sec. VIII, Div. 2 provide the rules to design the half-pipe jackets constructed of size NPS 2, NPS 3 and NPS 4. Both ASME Sec. VIII, Div. 1 and Div. 2 stipulates rules for calculation of minimum thickness of half-pipe jacket and the maximum permissible pressure in the half-pipe jacket.
Certain condition of applicability is provided in both ASME Sec. VIII, Div. 1 and Div. 2 to use the calculation procedure for design of half-pipe jackets.
1. There is positive pressure inside the shell/head.
2. There is positive pressure inside the half-pipe jacket.
Under certain situations, the above conditions may partially be met. e.g. The equipment may be under full vacuum with positive pressure in half-pipe jacket. Also, possibility could exist that the equipment is having some positive pressure while the half-pipe jacket may be experiencing vacuum simultaneously.
Such designs are not covered under the rules provided in nonmandatory appendix EE of ASME Sec. VIII, Div. 1 as well as in Part 4 of ASME Sec. VIII, Div. 2 and the users must demonstrate compliance by meeting U-2(g) for ASME Sec. VIII, Div. 1 and by designing in accordance with Part 5 for ASME Sec. VIII, Div. 2. For such design condition, elastic buckling and plastic deformation shall be evaluated for the entire equipment.
Unlike ASME Sec. VIII, Div. 1 and Div. 2, other international Codes like PD5500 and EN 13445 in addition to providing the rules for evaluating half-pipe jacket or limpet coils also states that when the equipment is subject to vacuum, the half-pipe jacket may be considered to contribute as stiffeners.
This paper is an attempt to find out the means to design the equipment with half-pipe jacket or limpet for which the conditions specified in ASME Sec. VIII, Div. 1 and Div. 2 are not satisfied.
Statistical Analysis of Localized Corrosion in Service Water Piping
Authors: Parker S. , Roukema A. , Patten Y. 
Published: October 2021

Abstract
Degradation found in carbon steel Service Water piping is typically characterized as localized corrosion or “pitting.” Localized corrosion or pitting is identified as small sections of thinning that deviate from the average wall thickness. In its most basic sense, a pit is simply a geometric entity that is abrupt and distinct that can range in size, extent, and density throughout the system. This raises the question of how one defines a pit and what geometric characteristics can be used to create this definition.
Research has been conducted to help provide answers to this question through detailed study of wall thickness examination results on operating service water piping in a nuclear power plant. This analysis has determined that the primary geometric characteristics are the depth-to-extent ratio, the extents of thinning, the shape of the pit, and the distance between adjacent pits. Statistical distributions of these characteristics for the evaluated data sets were developed to understand the overall trends of the pitting. With further research, the results of this evaluation can be used to extrapolate these trends of pitting characteristics, with high statistical confidence, to sections of service water piping that have little to no detailed non-destructive examination data. The objective of this paper is to present the preliminary findings of the statistical study on “pitting” and provide a set of geometric characteristics that best define a pit.
Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components
Authors: Barua B. , Jetter R. I. , Messner M. C. , Sham T.-L. 
Published: October 2021

Abstract
Current Class A materials qualified in the ASME Section III, Division 5 rules for high temperature nuclear service do not have optimal resistant to salt corrosion in fluoride salt-cooled high temperature reactor and molten fluoride salt reactor. This limitation can be overcome by using cladded components — overlay the Class A materials with a thin layer of some non-qualified corrosion resistant material. However, there are currently no ASME design rules for cladded components to guard against creep-fatigue failure and ratcheting strain accumulation in elevated temperature nuclear service. Therefore, design methods along with a complete set of design rules for cladded components were developed in [PVP2020-21469]. In order to support the near-term deployment of these advanced reactor systems, the underlying goal of the new design rules was to avoid relying on long-term test data of the clad materials. New design rules for two types of clad materials fulfill this requirement. They are soft clad materials that creep much faster and hard clad materials that creep much slower than the Class A base materials. This necessitates the development of criteria for selecting clad materials which fall into either the hard or soft category. A previous work [PVP2020-21493] developed such clad selection criteria for a Class A metallic alloy — Type 316H stainless steel. These criteria require comparing the minimum creep rate between the clad and base materials at different stresses and temperatures and therefore need some short term creep test data to develop a minimum creep rate model for the prospective clad materials. To reduce the creep testing effort for the clad materials this work develops a new set of clad selection criteria — requiring creep tests at a single condition or no test at all; thus it is much simpler to execute. Sample finite element analyses of a representative high temperature reactor vessel are performed to verify the clad selection criteria.
Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan
Authors: Yada Hiroki , Wakai Takashi , Miyagawa Takayuki , Machida Hideo 
Published: October 2021

Abstract
The leak before break (LBB) assessment guidelines for sodium cooled fast reactors (SFRs) is being developed in the Japan Society of Mechanical Engineers (JSME). The major purpose of the guidelines is to provide LBB assessment procedures for pipes and vessels of SFRs that retain sodium coolant. Design features of SFRs, such as high operation temperatures and low pressure coolant-systems, are taken into account. The LBB guidelines is used in connection to the fitness-for-service code that is also being developed for SFRs in JSME. If the establishment of LBB concept is successfully demonstrated, continuous leakage monitoring will be adopted as an in-service inspection for SFR components constituting sodium coolant boundary, such as sodium retaining pipe and vessels. The LBB assessment consists of three main paths, which are “Unstable fracture assessment”, “Leak rate assessment” and “Penetrated crack assessment”. “Unstable fracture assessment” is conducted to determine a critical crack length, ccr, which introduces unstable fracture under given loading conditions. “Leak rate assessment” is carried out to determine detectable crack length, cd, above which sodium leakage can be detected by installed leak detectors. In order to assess the cd, a new crack opening displacement evaluation method was developed for thin walled large diameter cylindrical structures taking the geometrical feature of SFR pipes into account. “Penetrated crack assessment” is performed to determine cp, the crack length when a crack penetrates the wall, under given transients hypothetically repeated enough cycles for the crack to penetrate the wall. In order to assess the cp, a simplified method was developed both for axial and circumferential cracks as a function of the ratio of membrane and bending stresses and fatigue crack growth characteristics. In the cp assessment, penetrated crack length is evaluated by considering only fatigue crack growth mechanism because penetrated crack length without considering creep effects becomes longer. If ccr is longer than both cd and cp, it can be concluded that the establishment of LBB concept is demonstrated. To demonstrate the procedure of LBB guidelines, actual SFRs piping was evaluated and the establishment of LBB concept is successfully demonstrated.
Development of Minimum Pressurization Temperature Envelopes for Hydroprocessing Reactors - A Case Study
Authors: Kagita Gurumurthy , Pudipeddi Krishnakant V. , Pottem Penchala S. K. , Achary Gudimella G. S. , Sripada Subramanyam V. R. 
Published: October 2021

Abstract
Low alloy heavy-walled hydroprocessing reactors in the refining industry, which operate at elevated temperatures and high hydrogen environments, need to be designed for protection against brittle fracture especially during start-up and shutdown. While developing minimum pressurization temperature (MPT) envelopes for these reactors, both temper and hydrogen embrittlement effects must be considered. However, there are no specific rules to evaluate loss of toughness due to hydrogen embrittlement in the design Codes / fitness-for-service Standards. Earlier, Japanese steel and pressure vessel manufacturers (JSPVM) developed a methodology to estimate MPT envelope for Cr-Mo steel pressure vessels. Recently, a state-of-the-art fracture mechanics based methodology is published in Welding Research Council (WRC) Bulletin 562 to determine MPT envelopes for equipment operating in high-pressure hydrogen environments. Meanwhile, API RP 934-F draft provided guidance on developing MPT envelops for heavy wall Cr-Mo vessels. In this paper, a brief summary of the JSPVM, API and WRC approach is presented with flow charts. A case study of establishing the MPT envelopes for a typical hydroprocessing reactor using WRC, JSPVM and API approach is presented and the results are compared and discussed. The advantages and potential savings of using recent WRC approach are highlighted.
Numerical Investigation on Local Thermal Buckling Behaviours of Buried Large Diameter Heating Pipeline
Authors: Yang Yue , Zhang Hong , Liu Xiaoben , Fang Weilun , Sun Lei , Feng Jibei , Gao Mingxu 
Published: October 2021

Abstract
The urban infrastructure serves as lifelines for the normal operation and sustainable development of the city. The heating pipeline is one of the most important infrastructures of the urban lifeline system. At present, the design of directly buried heating pipeline is mainly based on the stress failure criterion. Since the large diameter directly buried heating water pipeline is subjected to high temperature and high pressure loads, the initial state of the pipeline is in an elsato-plastic state, which makes the equivalent stress yielding criterion cannot be applied in this case. However, the existing elastic-plastic buckling analysis mainly focuses on the displacement or mechanical loading conditions, there is no reliable evaluation index to represent the true limit state of the heated pipeline. In this investigation, geometric configuration scanning tests were carried out for pipes with diameter equals 1020 mm. The actual nonstraightness and ovality of pipeline were statistically analyzed. Based on the true geometric model, nonlinear finite element models for thermal buckling analysis of buried large-diameter heating pipelines were established. The yielding, buckling and failure behaviors of this kind of thin walled shell structures under temperature loads in engineering practice were analyzed. Parametric analysis was finally performed to investigate trends of pipe stress, strain and deformation with the pipe loading and pipe geometric parameters. The derived results can provide guidance for the design and safety assessment of directly buried heating pipeline.
Digital Twin of Buried Oil Pipe in Permafrost Regions: A Multi-Source Monitoring and Numerical Simulation Model
Authors: Ji Beilei , Liu Xiaoben , Shi Ning , Liu Jianping , Chen Pengchao , Zhang Dong , Zhang Hong 
Published: October 2021

Abstract
Geohazards have become one of the major threats for pipeline safety as catastrophic consequences can be induced by the ground displacement. To prevent pipe failure, multi-source monitoring technics have been adopted by pipeline operators in engineering practice. While the strain gauge monitored strain results are discretely distributed along the pipeline, which makes the most dangerous pipe section might be not derived directly via sensors. Therefore, it is of great significance to establish an accurate numerical simulation model based on digital twin technology in the geological disaster areas to predict the actual stress and strain status in pipelines. In this paper, an automatically generated parametrical finite element model was established by combining using the general nonlinear finite element software package ABAQUS and the numerical calculation software MATLAB. Numerous numerical strain results were generated as database for a multi-layer backpropagation artificial neural network regressing pipe’s strain state and the geohazard loading conditions (i.e. soil displacement, length of the geohazard areas etc.). Finally, particle swarm optimization algorithm was employed to obtain the most fitting geohazard loading conditions based on monitoring data. An actual case of a buried X65 crude oil pipeline in northeast China was considered as an example, results show that after 5 iterations a relatively accurate strain distribution along the pipe was obtained via the optimization results. The proposed method can be adopted in the integrity management of pipeline crossing geohazard areas.
The Impact of Silicon Content on the Corrosion Resistance of Nickel-Molybdenum Alloy in High Concentration Sulfuric Acid Transport
Authors: Almomani Abdulla Fawzi , Alhaj Hazem , Ismail Mourad Abdel-Hamid 
Published: October 2021

Abstract
This failure case analysis highlights the impact of silicon content on the corrosion resistance of Ni-Mo alloy piping welding joints, known as Hastelloy B-2 (UNS N10665), in high concentration sulfuric acid (98 wt. % H2SO4) medium. A damaged piping weld joint is analyzed against an accelerated corrosion mechanism which was found to shorten the joints lifetime drastically. Superiority of B-2 alloys is largely attributed to the high concentration of molybdenum (26–30 wt. %) that gives its corrosion resistance to highly reducing acidic environments. However, certain deficiencies, such as short-range ordering (SRO) and intermediate phases formations (Ni4Mo transformation) in its metallurgical structure, in the as-welded conditions, was found to hinder its thermal stability. In this piping failure case analysis, close examination including optical assessment, X-ray fluorescence (XRF) spectrometry, and in-situ replication metallography were performed on a defected weld neck butt-fusion welding joint. XRF revealed a silicon content of almost four times (0.38% against 0.1%) the ASTM maximum requirements, which appears to have lowered the alloy’s thermal stability and increased its kinetics to rapid phase transformation (from α to β) along the grain boundaries. Extensive second phase precipitates were observed along the domain boundary interfaces in the microstructure, which is suggested to have resulted in Mo-depleted zones in the matrix. In this case analysis, the welding temperature (650–750°C) of NiMo alloys butt-joints along with the silicon content (0.1% to 0.3%) present were found as main contributors to the reduction of the welding corrosion resistance and hence to the shortening of the piping lifetime.
Developing a Weld Overlay Specification for Hyper Duplex Stainless Steel
Authors: Acuna Andres , Ramirez Antonio , Menon Ravi , Björnstedt Per-Åke , Carvalho Leonardo 
Published: October 2021

Abstract
Hyper Duplex Stainless Steels (HDSS) are dual phase, ferritic-austenitic materials with a remarkable yield strength (≥ 700 MPa) and corrosion resistance (PREN/W &gt; 49). It has been developed as an alternative to super-duplex stainless steels, where higher mechanical and corrosion performance is required. Unfortunately, such highly alloyed materials are susceptible to brittle intermetallic phase formation, such as the sigma phase. Understanding the intermetallic formation is essential to obtain its optimal properties and define advantages and limitations for a welding specification.
Overlay experiments on three-layered HDSS deposited over a carbon steel plate using 1.1kJ/mm and 1.65kJ/mm shown a clear austenite/ferrite phase ratio difference between the first and last layer. The last deposited layer has a larger ferrite volume fraction and chromium nitride presence. However, no sigma phase was found on the overlay conditions.
A sigma phase kinetic model was developed using Thermocalc Prisma, experimentally adjusted, and validated by physical simulation in a series of isothermal heat treatment tests. The additivity rule was used to calculate continuous-cooling-transformation (CCT) curves from the adjusted temperature-time-transformation (TTT) curves.
The kinetic model predicts no sigma precipitation for cooling rates faster than 4°C/s. Physical simulation with controlled cooling rates validated the model. Also, the thermal history analysis of the overlay experiments has shown no sigma was expected due to the total time and temperature transformation and cooling rates not reaching the calculated CCT.