bluuebunny/crossref_metadata_2025_split huggingface dataset:
Development and Application of Dynamic Monitoring System for Large Volume Winding Cylinder Tube Trailers
Authors: Yang Chao , Zhang Laiming , Luo Hui , Li Tong , Yu Yue , Chai Sen , Li Xiang 
Published: November 2024

Abstract
Large volume winding cylinder tube trailer as a typical mobile pressure special equipment in China is increasing rapidly, more than 500 new each year. Its transport medium is mostly flammable, explosive, corrosive and toxic compressed gas, with high safety hazards and potential dangers. The experimental research shows that fatigue times and fire accidents have an important impact on the safety performance of large-volume wound cylinders, resulting in liner cracking, wound layer failure, media leakage, explosion and other accidents. This paper intends to develop a monitoring system for the operation status of a large-volume winding cylinder long-tube trailer. By using pressure, temperature, medium concentration sensors, microprocessor, 4G communication, GPS and other technologies, a pressure monitoring and early warning system for a large-volume winding cylinder long-tube trailer is designed to realize remote real-time monitoring of the pressure of the long-tube trailer, and to give timely warning when the pressure of the cylinder is too high. Through the system simulation operation test, the normal operation of the system function is verified, which has certain feasibility and reliability to prevent the overpressure failure of the long-tube trailer gas cylinder, so as to realize the real-time monitoring of pressure and temperature, real-time alarm of media leakage, overtemperature and overpressure, and fatigue statistics of the long-tube trailer of large-volume winding gas cylinder as well as the variation law of defects with fatigue frequency is summarized.
A Multiple-Criteria Decision Application for Evaluating the Probabilistic Integrity Codes
Authors: Hanyi Niu , Guo Lingyun 
Published: November 2024

Abstract
To ensure the accuracy of probabilistic integrity in design, management and research, various codes have been established to assess safety and reliability of pipelines such as ProLOCA, PROST, xLPR, etc. They are refined and improved through benchmark projects (BPs), obtaining well-recognized research outcomes. However, BPs only compare the relative errors of the same calculation conditions and ignore the usability of the codes. Therefore, in further refining overall performance of probabilistic integrity codes (PICs), it is necessary to improve the usability.
This paper presents a novel application for evaluating the PICs, which is mainly divided into four main steps. Firstly, a multi-layer evaluation index system (EIS) is established which contains 3 layers and comprises three main aspects: Prediction Performance (PP), Software Usability (SU) and Option Diversity (OD). In the second step, we use the multi-layer best-worst method (MBWM) to determine the weights of different evaluation criteria. In the third step, a set of wv* experimental data is used to quantitatively mine the PP decision matrix, while the SU and OD decision matrixes are determined based on experience and expert knowledge. Finally, we adopt the sum weight method (SWM) to assess the overall performance of codes and provide suggestions for user selection and software optimization.
The Use of Tuned Mass Dampers in Mitigating Small-Bore Piping Vibration
Authors: Cheong Ian Ty 
Published: November 2024

Abstract
Vibration measurements of several small-bore pipework attached to a screw compressor package at an operating asset showed vibration levels more than the Energy Institute Guidelines “Problem” limit.
This presented a significant integrity threat to the operating asset. The piping vibration was primarily driven by pocket-pass frequency pulsations harmonics in the higher frequency range of 100–500 Hz.
Initial efforts to brace the pipework were not successful, likely due to the bracings inability to provide sufficient stiffness at higher frequencies. Following initial bracing attempts, a detailed vibration study and experimental modal analysis were carried out. The measurements were used to calibrate a dynamic finite element (FE) model of the small-bore piping. The predicted fatigue life of the worst affected pipework was 5.5 years.
The results of the FE model were used in the design of a tuned mass damper (TMD) to mitigate the vibration levels. During the design phase, the influence of the TMD on the dynamic response of the piping system was evaluated, however, this is not the primary focus of the paper.
Upon installation of the TMD, the vibration of the worst affected pipework showed a significant reduction of 73% and was no longer in the fatigue damage zone, which proved the effectiveness of the solution. This paper is intended to provide an overview of the concept of the solution, advantages of using TMDs and to share the results of this technique in mitigating piping vibration concerns where traditional methods (e.g: supports or bracing) may not be effective.
Technical Basis for Proposed ASME Section XI Code Case on Evaluation Requirements for a Static Over-Pressure Event in Class 2 or 3 Piping System
Authors: Xu Steven X. , Moenssens Mark , Antaki George , Pace Raymond 
Published: November 2024

Abstract
This paper presents the technical basis for a proposed ASME Section XI Code Case for assessing the structural integrity of a Class 2 or 3 metallic piping system after a static over-pressure event. Compliance with the required actions and acceptance criteria assures the piping system has adequate structural integrity to return to service.
ASME Code Section III NCD-3600 currently provides overpressure allowances for Service Levels C and D events that exceed the allowable working pressure calculated by ASME Section III NCD-3640 Eq. (5). NCA-2142.4, Design, Service, and Test Limits, defines the level of damage caused by Service Levels C and D events as possibly causing: “large deformations in areas of structural discontinuity” for a service Level C event, and “gross general deformations with some consequent loss of dimensional stability and damage” for a Service Level D event. However, NCA-2142.4, or Section III and Section XI in general, does not address the actions to be taken if these permitted Service Level C or D over-pressure allowances occur, or if the pressure exceeds the Service Level C and D limits. The proposed Code Case specifies the actions required in case of a static overpressure event that exceeds the allowable working pressure but remains within the bounds currently permitted for a Service Level C event, or an event that exceeds the over-pressure allowance currently permitted for a Service Level C event but remain lower than the Service Level D limit. Over-pressure events that exceed the ASME Section III Level D limit are not addressed in the proposed Code Case but are planned for a future revision to the Code Case.
CMC Components for HTR Design and Qualification Testing
Authors: Geringer Josina W. , Windes William 
Published: November 2024

Abstract
Ceramic Matrix Composites (CMCs) which include silicon-carbide silicon-carbide (SiC-SiC) and carbon-carbon (C-C) composite materials, for the use of core components for high temperature reactors in the American Society of Mechanical Engineers (ASME) Boiler Pressure Vessel Code (BPVC) Section III Division 5, were introduced due to their light weight, strength in extreme conditions and in some instances great neutron irradiation resistance. The code relies heavily on industry to align itself in the nuclear environment by using best practices adopted from others.
Over the years there has been a lot of emphasis on graphite qualification and component design, which is still a significant undertaking, but there is very little discussion on what it entails to follow a CMC component design and qualification process. According to Sec III-5-HHB, CMC’s only follows a Simple Assessment Method, as appose to graphite that has the option to follow either a Simple or Full Assessment Method. In addition, several test standards under the leadership of ASTM C28, have been developed to guide test methods. This paper focus on the optimization areas that have been identified since the first publication of ASME Sec III-5-HHB and it provides a roadmap to perform CMC materials qualification.
Exploration of the Effects of Response Spectrum Matching on Power Spectral Density Functions
Authors: Nie Jinsuo R. 
Published: November 2024

Abstract
Section 3.7.1, Revision 4, “Seismic Design Parameters,” issued December 2014, of the U.S. Nuclear Regulatory Commission document NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (SRP), provides acceptance criteria for seismic design acceleration time histories, which establish two sets of criteria: (1) the calculated response spectra (RS) from the time histories envelop the design response spectra (DRS), and (2) as a secondary check, the power spectral density (PSD) functions envelop the minimum target PSD functions that are compatible with the DRS. SRP section 3.7.1 also indicates that the PSD functions of closely RS-enveloped (or RS-matched) time histories fluctuate significantly and randomly as a function of frequency, and the fluctuations may lead to unconservative results for the response of structures, systems, and components. This explains the previous difficulties in meeting both RS and PSD enveloping criteria during the development of seismic design acceleration time histories. Such difficulties can potentially be relieved by a recently published wavelet-based time-domain RS-matching algorithm in Nuclear Engineering and Design, 410(112384), because that algorithm uses a minimal number of wavelets to achieve RS convergence and so allows a well-separated treatment of power assurance and RS matching. This paper explores, through examples, how that algorithm affects the PSD functions of the time histories and, more importantly, how it can help achieve both power sufficiency and the RS-matching criteria.
Verification of Earthquake Simulation Capabilities for Small Modular Reactor (SMR) Floating Seismic Isolation Systems
Authors: Tabbakhha Maryam , McCallen David , Miah Mamun , Nie Jinsuo , Wang Weijun , Graizer Vladimir , Pires Jose , Bauer Laurel 
Published: November 2024

Abstract
The ability to ensure robust seismic resilience is a critical requirement for all nuclear power plants (NPPs). There have been a number of innovative technologies considered for seismic response modification for NPPs, including application of traditional seismic base isolation technologies to ensure adequate earthquake performance. A unique response modification concept based on the utilization of a floating plant has recently been proposed. The underlying principle includes exploitation of the fact that shear waves cannot propagate through water, and floating a reactor building on a reservoir of water can isolate the reactor building from incoming earthquake-induced shear waves. The proposed system would also reduce seismic demand in the vertical direction by utilizing air cavities and orifices for enhanced damping. To explore the seismic performance of such a system, it is essential to have computational simulation models that can accurately represent the dynamic response of such complex systems. The objective of this work is to provide the U.S. Nuclear Regulatory Commission with the technical knowledge to appropriately evaluate the seismic performance of this type of innovative isolation system. In this article, existing finite element software programs are critically evaluated in terms of their ability to estimate the transient response of the floating isolation systems. A suite of numerical tests aimed at verifying the ability to appropriately represent gravity initialization of the model, fluid sloshing, and system transient response due to earthquake motions, are described.
ASME BPVC Treatment of Disparate Flaws in Graphite
Authors: Saitta Michael 
Published: November 2024

Abstract
Graphite is a quasi-brittle material that has recently become of great interest to designs of advanced nuclear reactors due to its excellent thermal and neutronic properties. When designing graphite core components for reactors, engineers must analyze the components for structural adequacy. Graphite is a quasi-brittle material with complex failure behavior. Of particular interest to this paper is the disparate flaw failure mode that results in low strength failures in some portion of graphite specimens. The nature of disparate flaws and their impact on the failure probability distribution of graphite is explored. To this end, historic data and literature is reviewed.
The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME BPVC) contains a set of rules to aid in the design and qualification of graphite core components. The current manner in which the ASME BPVC attempts to account for disparate flaws within the full assessment and its derivation is discussed. This method is shown to have a number of problems. Alternative methods for the handling of disparate flaws are provided and the benefits of each potential method is assessed. Based on the review of disparate flaw behavior and the methods by which they may be accounted for, the authors propose a path forward which allows reactor designs to have accuracy in estimated material reliability curves without the need for excessive testing or unrealistic conservatism.
Analyses, Mitigations and Reflections From Hydrogen Stress Cracking Failure of a Duplex Stainless Steel Reactor Effluent Air Cooler (REAC) in Hydrocracker Service
Authors: Hosack Allie , Idowu Oluwaseun , Barrass Jordan , Penso Jorge , Pudwill Wesley , Dalal Mitul 
Published: November 2024

Abstract
During start up following an outage for a major turnaround, a Duplex Stainless Steel Reactor Effluent Air Cooler (DSS REAC) leaked. The REAC was in a hot high pressure separation circuit of a refinery hydrocracker unit. Following the leak, detailed failure investigation was completed that revealed that the leak had occurred because of hydrogen stress cracking of the REAC tube-tubesheet welds. While the susceptibility of DSS REAC welds to hydrogen stress cracking in the form of sulphide stress corrosion cracking has been previously attributed to specific features from manufacturing, for example, ferrite-austenite phase imbalance and high hardness, over the past few years there is a growing body of evidence of the REAC DSS material experiencing cracking due to hydrogen embrittlement damage. This is despite having recommended controls in place during the original manufacturing stages. This paper will discuss the case history of the leak on the DSS REAC, including the details of failure analyses and engineering evaluation conducted on the cooler. This paper will also discuss some of the mitigations that were put in place, as well as provide reflections on the mode and mechanism of the damage.
Use of Plant Systems Design Standard (PSD-1) for Complying With Generic Design Assessment
Authors: Donavin Paul , Feldman Arnold , Pellereau Benjamin 
Published: November 2024

Abstract
This paper highlights the similarity between the United Kingdom’s General Design Assessment (GDA) with Plant Systems Design Standard (PSD-1). The three-phase approach in the GDA aligns with the PSD-1 design approach. The GDA has initiation, fundamental assessment, and detailed assessment. Each step builds in detail towards support of regulators’ decision process. The PSD-1 has initial design, preliminary design, and detailed design. These design actions have validation processes and risk evaluation as an integral part of the standard.
The advantage of the standard is to provide a uniform methodology with a consistent level of quality and a standard approach to risk evaluation. For the applicants, the PSD-1 provides a framework to prepare the required document to comply with the GDA. For the regulators, both nuclear and environmental, it provides an auditable approach to the preparation and validation of the submittal documents.
The beginning of the GDA is a project plan. Project Management has three key aspects for a project plan. The Scope is essential for developing the project plan. PSD-1 provides a disciplined approach to determine the scope of the submittal.
Risk assessment is a critical part of the GDA. PSD-1 has a detailed requirements for determining the risk of the plant beginning with a hazard assessment. The risk evaluation and determinations are carried through the design process as critical attributes.
Regulators rely on the quality of submissions to perform their reviews. The integrity of the PSD-1 process with required and planned validations helps ensure the submissions have reasonable assurance of accuracy and quality.
Investigation of Coke Drum Washer Plate Loosening and Top Nozzle Deformation
Authors: Dewees Dave , Baden Nick 
Published: November 2024

Abstract
A pair of operating coke drums recently experienced two events of abnormal vibration of the structure during coke cutting. Inspections after each event identified progressive loosening of base plate anchoring in both drums from the first instance to the second as well as increasing deformation of an antifoam nozzle. The antifoam nozzles on both drums were affected, with one nozzle developing a through-wall crack after the second event. This paper presents analysis to quantify the relationship between top-drum movement large enough to deform the nozzle and the resulting effect on the drum anchoring. A complete finite element model of the coke drum, skirt and anchoring is constructed using shell and beam elements. Both mechanical and thermal movements are imposed on the drum and the resulting bolt stresses and strains are evaluated to support root cause and integrity analyses. Results suggest only thermal bowing captures the observed anchor bolt behavior while still reproducing the needed top deflection to crack the antifoam nozzle. Cyclic analysis is performed over multiple thermal cycles that duplicates the progressive washer plate loosening/bolt-stretching observed in practice.
An Efficient Prediction Method for Critical Buckling Axial Compression Load of Corroded Pipelines
Authors: Fan Yuran , Zhang Tieyao , Shuai Yi , Shi Lei , Shuai Jian , Li Xingtao , Liu Haipeng 
Published: November 2024

Abstract
Corrosion and external loads are unavoidable problems in the operation of pipelines. It is of great significance to clarify the local buckling critical load of corroded pipelines under the influence of various parameters for pipeline integrity management and safety assessment. In this paper, a backpropagation neural network (BPNN) model with efficient prediction ability is established by combining finite element method (FEM) and machine learning (ML) method, which can realize rapid and accurate prediction of critical buckling axial compression load of X80 corroded pipelines with any 9 input parameters. Specifically, the accuracy of the 3D, nonlinear FE model was verified by experimental data, and then many buckling simulations of corroded pipelines with different input parameters were carried out. The data set with input-output relationship obtained by the FEM is used as the training data of the deep learning model. Through the hyperparameter debugging process, a 9-dimensional input layer, a 5-dimensional 80-node hidden layer and a 1-dimensional output layer BPNN model with deep learning and efficient prediction ability is established. Compared with the FEM, the prediction efficiency of this model has been significantly improved. Finally, the influence of corrosion defect geometry on the critical buckling load of corroded pipelines is studied by using the established efficient prediction model. It is clear that the defect depth and defect width have a great influence on the critical buckling load, while the larger defect length almost no longer affects the buckling load.
Effect of Pipe Geometry and End Conditions on Leak-Before-Break Assessment
Authors: Tregoning Robert , Wallace Jay 
Published: November 2024

Abstract
The Working Group for the Integrity and Aging of Components and Structures (WGIAGE), a working group under the Committee for the Safety of Nuclear Installation (CSNI), is conducting leak-before-break (LBB) benchmark activities. One activity in the Phase II benchmark consists of evaluating the effects of end restraint and piping compliance (ERPC) on LBB acceptability. While a classical LBB evaluation typically considers piping ends that are free to both rotate and displace, prior work has demonstrated that restrained-end conditions can substantially affect critical crack size and leakage crack size, thus LBB acceptability.
The ERPC benchmark topic compares identical piping systems where the end-restraint conditions vary, from both ends free to both ends fixed, as well as the distance of the flaw to the restrained ends. Prior analytical and finite element work from Miura and Kim et al., along with estimates of cracked section rotation from Brust et al., have been employed in an iterative solution for simultaneous convergence of leak rate (crack opening displacement) and crack stability predictions. Sensitivity analyses have been performed to assess the effect of total pipe length, pipe diameter, and wall thickness (i.e., pipe compliance), and the distance of the analyzed flaw to the end restraints. Crack tip plasticity effects have also been considered. Guidance has been developed for making engineering assessments of these effects and where unrestrained end conditions may be appropriate.