bluuebunny/crossref_metadata_2025_split huggingface dataset:
Level-3 Fitness-for-Service Assessment of Carbon Steel Piping Component Having Local Metal Loss
Authors: Rafique Muhammad Raheel 
Published: November 2023

Abstract
Carbon Steel (CS) lines operating under susceptible temperature range can have highly localized thickness loss due to Corrosion under Insulation (CUI), through penetration or entrapment of water or moisture and contamination due to external source (i.e. rain, marine environment etc.) underneath the external jacketed insulation. Thickness loss in the piping component beyond its corrosion allowance limit or minimum required thickness value (as per code requirements), requires Fitness-For-Service (FFS) assessment to ensure the mechanical integrity of the piping component, in order to continue the operation safely. In this work, the FFS assessment was performed for a Carbon Steel Line in Hydrocarbon service, having local metal loss beyond its minimum required thickness value at the vicinity of the structural discontinuity i.e. branched connection and its bracing to header weld joint. Level-3 assessment was performed considering Limit Load Analysis Method through Finite Element Analysis (FEA) as per acceptance criteria specified in API-579 Part-2 & 5. Where, all applicable loads were factored at multiple load steps, and the convergence of the solution was ensured up to the acceptable load limit step. The results of the analysis then used to predict the remaining life of the piping component, ensuring the protection against gross plastic collapse due to low thickness.
Pitting Corrosion Resistance in the Heat-Affected Zone of No-Backing Gas (NBG) Austenitic Stainless Steel Welds
Authors: Cary Claire , Penso Jorge , Sridhar Narasi , Fink Carolin 
Published: November 2023

Abstract
Stainless steel welds for service applications in corrosive environments are typically performed using gas tungsten arc welding (GTAW) with an inert backing gas in order to minimize or prevent root pass contamination and oxidation. Back purging adds significant cost and complexity to stainless steel pipe welding due to access restrictions, personnel safety, and/or economic factors. In this study, two no-backing gas welds (NBG) were made on Type 304L austenitic stainless steel pipe with Type 316 filler metal. Two different shielding gas mixtures were used (98% Ar-2% CO2 and 90% He-7.5% Ar-2.5% CO2) for the NBG welds. Open gap root pass welds were performed using modified short circuit gas metal arc welding (SC-GMAW) process. A hot pass was welded with pulsed GMAW process. Fill and cap passes were made with flux-cored arc welding (FCAW) process. Cyclic potentiodynamic polarization (CPP) measurements based on ASTM G61 were performed locally on the backside surface heat-affected zone as a function of distance from the fusion line. Electrochemical corrosion testing was done using a simple syringe cell setup. Pitting corrosion resistance of the NBG welds was compared to a reference weld made with 100% argon backing gas and conventional GTAW for the root and hot pass.
Advances and Challenges in Powder Metal Hip Processing for the Production of Large Components
Authors: Peters Daniel T. , Gandy David W. , Puerta Doug , McLaughlin Robert 
Published: November 2023

Abstract
There has been a significant movement in advancing the use of large hot-isostatically pressed (HIP) powdered metal parts in various industries recently. This is driven by a desire to reduce lead times, generate near-net shaped components, eliminate welds, improve inspection characteristics, and to address other constraints for applications where large forgings and castings are currently used in several industries.
Much of this interest in large HIP technology is currently being driven by the near-term commercialization of small modular reactors (SMRs) and advanced reactor (ARs) throughout the world, but particularly within the USA[1]. A consortium within the USA has been investigating the design of a large, 160 inches (4.05m) diameter × 160 inches (4.05 m) length HIP for several years now and hope to move toward manufacture of a large HIP unit within the next 18 months. Similarly, in the UK a slightly larger HIP unit (∼4.5m) referred to as Titan is also being considered. Interest is also growing in other countries including Korea, Sweden, and Japan towards design and production of a large HIP unit to support nuclear and other applications.
This paper is an attempt to summarize recent advancements in developing an ultra-large HIP system and discuss challenges in developing HIP equipment of this scale.
Pipe Plugs: A Survey of Historical Development and Current Technology
Authors: Cornelius Austin E. , Garza Armando , de Leon John Rey , Sallee Richard , Sue Casey 
Published: November 2023

Abstract
Piping isolation and gripping test plugs have been utilized for many years to evaluate and maintain the integrity of pipe and piping systems, yet accidents still occur resulting in damage to equipment, lost time, personnel injury, and death. Fluid processing often requires high temperatures and pressures. Some of the fluids present chemical hazards to personnel, the environment, and equipment. In order to ensure that this hazardous, but important work can take place as safely as possible, pipe plugs have been developed to help isolate, test, and validate the related systems and equipment for use. Over the last half century the petrochemical industry has increased the emphasis on safety. Recently, for example, the Post Construction Committee of the American Society of Mechanical Engineers has addressed many issues for safe pressure testing in the recommended practices of ASME PCC-2. While many of these improvements are on the procedural side, recently there has been a significant push in industry to improve the safety and limit the damage to the piping systems under test by improving the underlying technology.
What follows is an account of the developmental history of the technology, including how each successive innovation has made improvements as well as noting their limitations. The newest innovations represent a step change in reliability and safety for both personnel and equipment, some by making significant changes from previous gripping plug designs. It is of critical importance that those responsible for deciding which technology to use for their particular service and/or testing needs are aware of the inherent safety and reliability concerns with older gripping devices, which, in some cases, are still sold and used. These new developments have the potential to save money by reducing test preparation time, and reducing or eliminating the need for post-test repairs or removal of portions of the pipe damaged by the grippers. Responsible parties should be aware that new innovations now exist which could potentially save lives and reduce cost by decreasing the risk of serious accidents.
Deterministic Leak-Before-Break Treatment of Uncertainties: Part 1 – Theoretical Basis
Authors: Kozluk Michael J. , Al-Dojayli Maher , Pavia Renita , Mileta Ernie 
Published: November 2023

Abstract
The Canadian CANDU® Industry has developed and is implementing a composite analytical approach (CAA) to demonstrate, with high confidence, appropriate safety margins for deterministic nuclear safety analysis of large-break loss-of-coolant accident events in existing CANDU reactors. A key element of the CAA is the deterministic leak-before-break (CAA/DLBB) assessment for postulated through-wall cracks in all butt welds in the large-diameter primary heat transport system piping and reactor headers.
This paper describes a systematic approach for quantifying the uncertainty in the CAA/DLBB assessment. The proposed approach integrates the uncertainties of the key leak-rate parameters into a single metric (a quantitative indicator of the uncertainty in the CAA/DLBB assessment, a.k.a., performance indicator). This approach ensures that the uncertainty in individual key parameters is not taken out of the context of the uncertainty of the other key parameters. A brief description of the CAA/DLBB evaluation process is presented and the leak-rate factor is adopted as the figure of merit. Next, the key leak-rate effect factors are identified and the uncertainty in each is established. This is followed by a description of two statistical approaches that can be used to propagate the uncertainties for the bounding postulated break location and to determine the level of uncertainty associated with the CAA/DLBB assessment. In Part 2 of the paper, the application of the approach is illustrated.
Structural Integrity Assessments of Nuclear Graphite: Managing Uncertainty and Variability
Authors: Horne Graeme , Young Amanda , Kent Daniel , Gray Richard , Joyce Mark 
Published: November 2023

Abstract
The UK has decades of experience designing, operating and extending the lives of graphite moderated reactors, including the currently operating fleet of EDF’s Advanced Gas-cooled Reactors (AGR). This paper summarises some of the analysis used to substantiate the graphite safety cases for their continued operation. In particular, the use of graphite brick modelling, using a physically-based material model, to describe the behaviour of irradiated graphite. The material model is calibrated to measurements made during regular inspections of the cores, capturing variability and uncertainty in addition to a central estimate. A probabilistic wrapper is applied to the brick modelling, to make predictions of the onset and rate of keyway root cracking, which is a damage mechanism of particular concern. It is hoped that this experience can help inform the development of design codes required for the proposed future graphite-moderated reactor technologies.
Plant Validation of Flaw Evaluation Procedure for Axial PWSCC in Alloy 600 Reactor Vessel Head Penetration Nozzles
Authors: Fuhr Kevin , Schmidt Gideon , White Glenn , Harrington Craig 
Published: November 2023

Abstract
The analytical flaw evaluation procedure of Subsubarticle IWB-3660 and Nonmandatory Appendix O of the ASME Boiler and Pressure Vessel Code, Section XI is available to PWR licensees to disposition the detection of primary water stress corrosion cracking (PWSCC) in Alloy 600 reactor vessel head penetration nozzles. This procedure can be applied to accept a detected axial flaw for continued service if the flaw dimensions projected to the end of the evaluation period do not exceed the acceptance criteria of Table IWB-3663-1. The crack growth prediction for future operation must consider the PWSCC crack growth due to applicable loadings, including the tensile weld residual stresses that can dominate the stress state.
Following the detection of leakage in an Alloy 600 reactor vessel closure head control rod/element drive mechanism (CRDM) penetration in a U.S. PWR, a retrospective review of examination data provided several operating cycles of size information for the axial PWSCC flaw in the nozzle that was determined to be the cause of the leakage. This experience is a unique opportunity to compare the detailed data for flaw size evolution with the PWSCC growth predicted for the earliest observed flaw dimensions per the Section XI flaw evaluation procedure as a validation exercise.
Development of Code-Specific RSFa for Use in API 579-1/ASME FFS-1 Assessments
Authors: Nunez Joseph , Hay Clifford , Bedoya Julian 
Published: November 2023

Abstract
For metal loss assessments in the 2021 edition of API 579-1/ASME FFS-1 (hereinafter “API 579”), the Remaining Strength Factor (RSF) is “utilized to define the acceptability of a component for continued service.” The RSF is defined as the ratio of the plastic collapse load of the damaged component divided by that of the undamaged component. For metal loss assessments, the RSF is a function of the corroded geometry, as evidenced in the equations in Part 5 of API 579 and as documented in WRC 505. If the calculated RSF is less than an allowable RSF (RSFa), then the MAWP of the component must be reduced by the ratio of RSF/RSFa; otherwise, the component is acceptable at the undamaged MAWP. The recommended value for RSFa in API 579 is 0.90.
The 2007 edition of API 579 included Table 2.3 which provided recommended RSFa values based on the construction code, although the value of RSFa was listed as 0.90 for all codes in the table; the inclusion of this table (which was subsequently removed in the 2016 edition) was ostensibly for the purpose of eventually providing different values for different construction codes. To provide different values of RSFa, a permissible stress value distinct from the construction codes is needed, such that the RSFa for each construction code could be adjusted to provide a constant margin against burst pressure. This approach does not eliminate the possibility of including penalizing factors for certain construction details and/or codes which have less-rigorous inspection requirements or for similar reasons.
In a prior ASME PVP paper (PVP2022-84710), a generic equation was introduced to allow for quantification of the likelihood of ductile failure as a function of applied stress based on the semi-log assumption in API 581 (i.e., in the section related to pressure relief devices). Leveraging this approach, this study introduces an equation for a code-specific RSFa which allows for a constant margin against burst pressure for different construction codes.
Comparison of the proposed RSFa definition across different construction codes is illustrated with an example.
Shear Layer Instability in the Gap of Tandem Cylinders and Its Coupling With Higher Order Acoustic Modes
Authors: Noufal Rasha , Mohany Atef 
Published: November 2023

Abstract
This paper presents an experimental investigation of the aeroacoustic response from tandem cylinders in cross flow at different positions with respect to the acoustic particle velocity nodes and anti-nodes of different cross-modes. The objective is to better understand the role of the shear layer instability in the gap between the cylinders on the excitation of acoustic resonance and its coupling with higher-order acoustic modes. The results show that the tandem cylinders’ position with respect to the acoustic particle velocity anti-nodes of the cross-modes is a significant factor in determining the excitation of the dominant acoustic mode. Moreover, placing multiple rows of tandem cylinders at various positions with respect to the acoustic standing waves of the cross-modes in the duct promotes the coupling between the shear layer instability and the acoustic modes, even for the cases that didn’t trigger such excitation when the tandem cylinders were placed in a single row.
Development of a Web-Based Design Evaluation Platform for Elevated Temperature Design as per ASME Section III Division 5, ASME CC-2843 and RCC-MRx
Authors: Lee Hyeong-Yeon , Nam Ki-Ean , Huh Nam-Su , Kim Min-Kyu 
Published: November 2023

Abstract
An integrated web-based design evaluation platform of HITEP (HIgh Temperature design Evaluation Program) covering the three elevated temperature design rules of ASME BPVC Section III Division 5 Subsection HB (hereafter ‘ASME-HB’), ASME Code Case 2843-2 (hereafter ‘CC-2843’) and RCC-MRx, in addition to light water reactor design rules of ASME BPVC Section III Division 1 Subsection NB (hereafter ‘ASME-NB’) has been developed. CC-2843 is recently published code case of ASME Section VIII Division 2 based on the ASME-HB procedures with explicit consideration of creep. The evaluation module of ASME-NB has been added because the low-temperature design evaluations should be also conducted for a high-temperature component depending on temperature fluctuations. The HITEP platform can be used with high reliability and efficiency for the design of high temperature pressure boundary components or piping systems subjected to high-temperature operation at creep regime in a Generation IV nuclear reactor systems, renewable plants and advanced thermal power plants. In addition to those high-temperature applications, the platform can be applied to design of Generation III+ light water reactor systems. It was shown that the platform can be reliably and efficiently used for the elevated temperature design (hereafter ‘ETD’) of pressure boundary components and piping systems. The HITEP platform has been successfully used for the ETD of pressure boundary components and piping systems of the two large scale sodium test facilities of the STELLA-2 that is currently under operation and the thermal energy storage test facility of the TESET that is under construction at KAERI.
Creep-Fatigue Life Evaluation of Modified Grade 91 Tube Sheet Structures Under Flexible Loading Conditions
Authors: Islam Nazrul , Hossain Md Sumon 
Published: November 2023

Abstract
This study evaluates the creep-fatigue strength of a tube-sheet structure using elastic and inelastic constitutive models based methods. Such a tube-sheet structure of the Sodium Fast Reactors (SFR) developed by the Japan Atomic Energy Agency is one of the critical components to design because of its complex structural geometry. The creep-fatigue loading condition of SFR is also a challenge to properly address the combined effect of the loading condition, especially at the critical locations of the components like the numerous holes. Hence, this study develops a 3D FE model of the SFR’s tube-sheet structure to evaluate the combined creep-fatigue damage. The test model was subjected to ten years of severe thermal flexible loading conditions using a large-scale sodium loop, in which elevated-temperature sodium at 600°C and 250°C was flowed repeatedly and kept at the final temperature for 10 years and 1h. Similar start-up and shutdown conditions are maintained for 12 months and 1h, 6 months and 1h, 3 months and 1h, 1 month and 1h, respectively. Using the sodium temperature data obtained during the test, heat transfer analysis and stress analysis were carried out. Various constitutive models are used for the evaluation of creep-fatigue. The creep-fatigue life of the component is initially determined using elastic analysis-based stress redistribution locus and simple elastic follow-up methods. These elastic analysis-based methods are compared with the inelastic constitutive models e.g., bilinear and Chaboche model coupled with time hardening creep. Finally, the effect of flexible operation conditions is evaluated in the Campbell diagram with the elastic and inelastic analysis-based methods to show the applicability of these methods for life prediction.
A Survey of Failure Rate of In-Service Pressure Vessels in China’s Non-Nuclear Industry
Authors: Song Libin , Li Jun , Han Zhiyuan , Xie Guoshan , Deng Guide , Li Zhifeng 
Published: November 2023

Abstract
Failure rate is very important for the reliability and risk assessment of in-service pressure vessels. As early as in the 1970s and 1980s, the failure rate data of in-service pressure vessels has been collected in various countries, such as Europe and the United States, and in great detail. These data were incorporated into the relevant reliability database such as OREDA and CEMHD5. However, the failure rate data of pressure vessels in China is rarely reported so far, which limits the development of reliability and risk assessment technology for the pressure vessels in non-nuclear and nuclear industries. In this paper, about fifty thousand in-service pressure vessels data in China’s non-nuclear industry were collected. The potential and catastrophic failure rate were counted based on exponential distribution model. The statistical results were compared and analyzed with those of other countries such as the United States, the United Kingdom and Germany. The analysis results showed that the thickness thinning and cracking caused by corrosive medium were two main causes for pressure vessel failures in China. The failure rate of in-service pressure vessels in China is higher than that in the Europe and the United States countries, which may be caused by the high sulfur and high acid crude oil.
A Failure-Probability- and Damage-State-Based Fatigue and Creep Model for Estimating Reliability of Stainless Steel 316L(N) Components in Thermal Fatigue
Authors: Fong Jeffrey T. , Marcal Pedro V. , Cohn Marvin J. , Heckert N. Alan 
Published: November 2023

Abstract
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) Committee has recently developed a new Section XI (Nuclear Components Inspection) Division 2 Code named “Reliability and Integrity Management (RIM).” RIM incorporates a new concept known as “System-Based Code (SBC)” originally due to Asada and his colleagues (2001–2004), where an integrated approach from design to service inspection is introduced using three new types of statistical quantities: (1) “system reliability index,” or “system co-reliability target” for any system consisting of structures and components, (2) “structural co-reliability,” for any structure, and (3) “component co-reliability” for any component, where co-reliability is defined as “1 – reliability” and is equal to failure probability. In a recent paper published in the International Journal of Pressure Vessels and Piping (Vol. 173 (2019), pp. 79–93). Fong, Heckert, Filliben, and Freiman developed a new theory of fatigue and creep rupture life modeling for metal alloys at room and elevated temperatures such that the co-reliability of a smooth component can be estimated from fatigue and creep rupture test data with simple loading histories. In this paper, we extend the theory to include a methodology to estimate the failure probability (or, co-reliability) of a stainless steel 316L(N) component undergoing a complex loading history such as a thermal fatigue cycle. To illustrate an application of this new modeling approach, we present a numerical example using (a) the experimental test data of 7 specimens of S.S. 316L(N) in creep at 565 C as published by Kilian Wasmer in his Ph.D. thesis (Imperial College London, 2003), (b) the experimental test data of 10 specimens of S.S. 316L(N) in creep at 650 C also by Wasmer (Ph.D. thesis, 2003), and (c) a thermal fatigue loading history of 1 hour of creep at 650 C at an operating creep stress of 73 MPa, and 300 hours of creep at 565 C at the same creep stress to simulate a hypothetical powerplant thermal fatigue operation. The significance and limitations of this new damage-state-based approach to modeling creep and to estimate the component failure probability (or, co-reliability) of steel components in creep at elevated temperatures with complex histories are discussed.