bluuebunny/crossref_metadata_2025_split huggingface dataset:
Wettability of saliva substitutes across various denture base fabrication techniques
Authors: Mikhail Paul , Pesun Igor , Azpiazu‐Flores Francisco , França Rodrigo 
Published: November 2024

AbstractPurposeThe present study evaluated the contact angles (CAs) of four denture base materials subjected to different surface treatments using deionized water and saliva substitutes.Material and MethodsA total of 32 rectangular specimens were manufactured using four different denture base materials: heat‐cured compression molded Lucitone 199 (C), milled Lucitone 199 (M), Formlabs Denture Base RP (P), and SR Ivocap High Impact (I). The CA of the surface of the unaltered, mechanically polished, and sandblasted surface specimens was evaluated after the application of five saliva substitutes: Biotene, VEGA, Spry, Moi‐Stir, Dentilube, and ionized water. Ten droplet measurements were obtained for each group, with each droplet analyzed for advancing contact angle (ACA), receding contact angle (RCA), and the contact angle hysteresis (CAH) was calculated. The data of the experiment was analyzed using 2‐way ANOVA, (α = 0.05) with Tukey's test.ResultsCAH was demonstrated to have statistically significant differences among the denture bases (p < 0.05), with unaltered 3D printed exhibiting the largest CAH, followed by unaltered milled. The unaltered denture bases exhibited higher CAH than the polished, and there were no significant differences in CAH among the polished denture bases (p > 0.05). Sandblasting increased the ACA of the milled and conventional bases. The saliva substitutes exhibited differences in ACA, with Spry and VEGA having the highest ACA, and Biotene had the lowest CA of all the saliva substitutes evaluated.ConclusionThe manufacturing methods of denture bases influences the CAH, while the chemical composition of the denture base specimens does not appear to affect CAH. Sandblasting increases the ACA for the milled and conventional groups. Saliva substitutes do impact the ACA. Drawing from previous research, it is hypothesized that a 3D‐printed denture base or sandblasting a milled denture base may offer greater resistance to dislodgement.
Characterization of DetaClad™ Interface With Simulated Weld Overlay Repair: A Positive Assessment for Cost and Time Savings in Equipment Lifecycle
Authors: Sarrat Olivier , Stolz Philipp , Wilson Chris , Delahanty Tim 
Published: November 2024

Abstract
In the context of equipment repair and refurbishment, in situ weld overlay on top of existing cladder is not a common practice. Concerns exist regarding the interface’s ability to withstand stresses induced by the weld overlay. This study aims to comprehensively characterize the DetaClad™ [1] interface and its behavior after simulating a weld overlay repair.
When considering weld overlay repair options, preserving the cladding emerges as a highly favorable choice. Weld overlay on top of the cladding offers a cost-effective, time-efficient, and prudent approach to refurbishing critical components. By retaining the cladding, the method minimizes disruption to the base material, preserving its integrity and essential mechanical properties. Moreover, this approach prioritizes safety by mitigating potential hazards during the gouging process.
The purpose of this research is to demonstrate that weld overlay build-up on top of DetaClad does not compromise the bond quality, nor the mechanical properties of the steel. The test parameters include analyzing the mechanical properties of the interface before and after welding, along with a detailed examination of the mechanical and structural properties of the base and cladder material. In addition, cross section macro and micro examinations are performed to gain valuable insights into their structural integrity.
This study demonstrates that weld overlay on DetaClad-cladded surfaces preserves the interface integrity and mechanical properties of the pressure boundary.
Comparison of Three Design Assessment Approaches for a 2-Liter Containment Vessel of a Plutonium Air Transport Package
Authors: Bignell John , Gilkey Lindsay , Flores Gregg , Ammerman Douglas , Starr Michael 
Published: November 2024

Abstract
Sandia National Laboratories (SNL) has completed a comparative evaluation of three design assessment approaches for a 2-liter (2L) capacity containment vessel (CV) of a novel plutonium air transport (PAT) package designed to survive the hypothetical accident condition (HAC) test sequence defined in Title 10 of the United States (US) Code of Federal Regulations (CFR) Part 71.74(a), which includes a 129 meter per second (m/s) impact of the package into an essentially unyielding target. CVs for hazardous materials transportation packages certified in the US are typically designed per the requirements defined in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PVC) Section III Division 3 Subsection WB “Class TC Transportation Containments.” For accident conditions, the level D service limits and analysis approaches specified in paragraph WB-3224 are applicable. Data derived from finite element analyses of the 129 m/s impact of the 2L-PAT package were utilized to assess the adequacy of the CV design. Three different CV assessment approaches were investigated and compared, one based on stress intensity limits defined in subparagraph WB-3224.2 for plastic analyses (the stress-based approach), a second based on strain limits defined in subparagraph WB-3224.3, subarticle WB-3700, and Section III Nonmandatory Appendix FF for the alternate strain-based acceptance criteria approach (the strain-based approach), and a third based on failure strain limits derived from a ductile fracture model with dependencies on the stress and strain state of the material, and their histories (the Xue-Wierzbicki (X-W) failure-integral-based approach). This paper gives a brief overview of the 2L-PAT package design, describes the finite element model used to determine stresses and strains in the CV generated by the 129 m/s impact HAC, summarizes the three assessment approaches investigated, discusses the analyses that were performed and the results of those analyses, and provides a comparison between the outcomes of the three assessment approaches.
Effect of Temperature on Hydrogen Assisted Fatigue Crack Growth Rate of an Austenitic Stainless Steel
Authors: Michler Thorsten , Varfolomeev Igor 
Published: November 2024

Abstract
The fatigue crack growth rate (FCGR) of austenitic stainless steel 1.4404 was measured in uncharged and in gaseous hydrogen precharged conditions, both as a function of temperature. At room temperature and ΔK &lt; 40 MPa m0.5, the FCGR of gaseous hydrogen precharged 1.4404 is by a factor of about 5 higher compared to the uncharged condition. FCGR as a function of temperature revealed a broad maximum at temperatures between 293 and 333 K. The temperature of maximum FCGR does not correlate with the temperature of maximum loss of tensile RA, which is about 220 K. A simplistic interpretation based on the respective governing mechanism, HEDE for FCGR tests and HELP for tensile tests, is proposed.
Ultrasonic Testing in Lieu of Radiographic Testing: Application to ASME III Class 1 Nuclear Pressure Vessels in the Context of Rolls-Royce Structural Justification Expectations
Authors: Whitehead David , Rice David 
Published: November 2024

Abstract
Volumetric inspection of major welds with Radiographic Testing (RT) methods is typically required for nuclear pressure vessels designed and manufactured in accordance with Section III of the ASME Boiler and Pressure Vessel Code. A number of ASME Code Cases exist which allow the RT prescribed within certain Sections of the Code to be substituted with Ultrasonic Testing (UT). Of particular interest, Code Case N-659 allows the use of UT in lieu of RT during the construction of Section III - Subsection NB nuclear pressure vessels.
The use of UT in lieu of RT during the construction of nuclear pressure vessels has the potential to unlock several attractive benefits. Substantial reduction in radiological safety risks during construction can be achieved as the need for radiological sources is reduced, particularly for thick section welds where high power sources are required. Flexibility during vessel construction is also improved, allowing either UT or RT to be deployed based upon the availability of operational resource and shielded RT enclosures.
Rolls-Royce designs nuclear pressure vessels in accordance with the principles of the ASME Boiler and Pressure Vessel Code. In addition to the ASME Code, Rolls-Royce implements a structural integrity policy, which considers the UK Technical Advisory Group on Structural Integrity (TAGSI) four-legged safety case approach. This approach promotes defence-in-depth through four conceptually distinct arguments (legs), to construct a robust safety argument.
This paper discusses the application of the N-659 Code Case within the context of Rolls-Royce structural justification expectations, including consideration of the TAGSI four-legged safety case approach.
A Standard Form for Cyclic Plasticity Models Used With the ASME Section III, Division 5 Rules
Authors: Messner Mark C. 
Published: November 2024

Abstract
Recent work by the ASME Boiler & Pressure Vessel Code Committees has produced a new nonmandatory appendix to Section III, Division 5 providing guidance and approved constitutive models for the Section III, Division 5, Subsection HB, Subpart B design by inelastic analysis rules. This appendix, along with the associated Code Cases, includes approved material models for three Class A materials. A fourth model, for Alloy 800H, has also been created and is currently being reviewed by the code committees. Currently, all four of these material models has a different mathematical form. This complicates the process of implementing and applying these models. This work describes a single, standard model form that can describe the high temperature, cyclic behavior of all four materials with reasonable accuracy. Specifically, we describe the need to alter the standard viscoplastic flow rule used with the Chaboche model for cyclic plasticity in order to accurately describe both cyclic deformation and creep at the onset of the creep regime. We propose a Kocks-Mecking type flow rule that can describe both viscous creep, at low stresses, and nearly rate-independent deformation at higher stresses. This paper also provides the calibrated material coefficients for the four Class A materials and describes the process of training these parameters against the available test data.
Review of Original Calculations and pc-PRAISE Source Code Used to Develop ASME Code Section XI Appendix L Equivalent Single Crack Tables
Authors: Xu Steven X. , Glunt Nathan , Shim Do Jun , Stevens Gary L. , Scarth Douglas A. 
Published: November 2024

Abstract
ASME Section XI Appendix L permits the use of flaw tolerance procedures to determine the allowable operating period for operating plant components and piping subjected to cyclic loadings, providing NDE confirms that the location of interest has no flaw larger than allowed by the Acceptance Standards. The flaw tolerance analysis postulates a pre-existing flaw at the location of interest and calculates fatigue crack growth to determine inspection intervals necessary to assure that the fatigue-growing flaw can be detected before it exceeds the allowable size. To account for the possibility of multiple flaws coalescing and forming longer flaws during the fatigue crack growth, the postulated single flaw is assigned with an aspect ratio, known as the ESC (equivalent single crack) aspect ratio, based on the applied loading and material type.
As part of the activities undertaken by the Section XI Task Group on Appendix L, an effort was made to conduct a detailed review of the original calculations performed to develop the Appendix L ESC tables and the pc-PRAISE source code that was used for those calculations. This effort was necessary because the available Appendix L and pc-PRAISE technical basis documents do not contain all the necessary details to reproduce the ESC tables, and there were knowledge gaps that prevented a complete understanding of the original technical basis. This paper documents the review findings and their impacts on calculating ESC so that future improvements to Appendix L can be considered appropriately.
The Truth About Double Nutting
Authors: Thibodeaux Brett 
Published: November 2024

Abstract
There have been several studies performed that pertain to the use of two nuts to prevent self-loosening; however, these studies do not focus on accuracy of the final bolt load achieved nor do they quantify the proper procedure for ensuring an adequate jam is achieved. A thorough understanding of the interaction of the bolt elongation during this tightening process is necessary to avoid inadvertent reduction in ability to prevent self-loosening.
Testing is used to record the behavior of the nuts, bolts, and bolt load achieved during the tightening process while performing variations of double nutting assembly procedures to confirm the interaction between tightening methods, the resultant bolt load, and whether a jam is achieved.
Structural Analysis of a Light Water Small Modular Reactor Under Coolant Recirculation Conditions
Authors: Choi Dong-Hyeon , Chang Yoon-Suk 
Published: November 2024

Abstract
U.S. Nuclear Regulatory Commission proposes a method for evaluating integrity of reactor vessels (RVs) against pressurized thermal shock (PTS) via the code of federal regulation. Before evaluating the PTS, dominant locations of a postulated crack should be selected considering effects of thermal-hydraulic loads. Recently, with the development of a light water small modular reactor (SMR), substantial changes have made in the emergency core cooling system as a part of passive safety design that releases and condenses steam forming a pool outside the RV and recirculates it. The objectives of this research are to numerically investigate structural behaviors of the RV subjected to supercooling loads and significant pressure generated by external fluid. A typical coolant recirculation scenario was assumed based on the height of recirculation valve, temperature, and flow rate as variables. Firstly, the transient data of the coolant were derived through systematic computational fluid dynamics simulations for eight cases. Subsequently, accompanying structural analyses were performed to quantify stress states, which are used for selecting the crack location. Finally, sensitivity analyses were conducted to assess interaction of parameters and contribution of each parameter. As results, for the developing light water SMR, dominant locations and variables were determined under the coolant recirculation scenario, and relevant features were discussed.
Radial Displacement Measurement of Hydrogen Storage Cylinders Under Internal Pressure Based on Fringe Projection Profilometry
Authors: Ying Kaidi , Ma Li , Wen Ange 
Published: November 2024

Abstract
Composite gas cylinders, as an important hydrogen storage device for hydrogen fuel cell vehicles, require a hydrostatic test to ensure safe usage and service. However, there is a lack of a non-contact and efficient method to monitor the deformation of the gas cylinders during the hydrostatic testing. Thus, this paper proposes a radial displacement measurement method based on binocular fringe projection profilometry (BFPP) for pressurized hydrogen storage cylinders. We use BFPP as a highly sensitive three-dimensional (3D) shape measuring method, where the shape information that encoded in the deformed light pattern is acquired based on phase demodulation and coordinate reconstruction. Combining with 3D morphology measurement technology, internal pressure loading tests were conducted on a composite overwrapped pressure vessel with 55 Litre and 35MPa design pressure. Firstly, a large-field BFPP system was constructed to collect 3D point cloud data of the surface of the cylinder at different internal pressures. Then, a cylinder fitting based on the least squares method was used to obtain the radius. Finally, the difference of radius between pressure load steps was calculated, which indicates the radial displacement of the gas cylinder at different internal pressures. The measured result shows a good agreement with FEA calculations, where the radial displacement increase linearly with the increment of inner pressure. The error ranges from 2% to 18%.
Expanding the API 579-1/ASME FFS-1 Stress Intensity Factor Solution for a 360 Degree Surface Cracked Bar (KBSCL)
Authors: Altstadt Steven , Sarzynski Melanie 
Published: November 2024

Abstract
The current library of API 579-1/ASME FFS-1 2021 Fitness-For-Service stress intensity factor solutions includes round bars with various surface crack configurations. However, for all listed crack configurations, the stress intensity factor solutions are limited to axial membrane and global bending stress inputs. These stress inputs can be insufficient for some fitness for service applications. Considering this, a long-term effort is underway by the authors and others to expand the stress intensity factor solutions to accommodate generalized stress distributions for all applicable cracked round bar configurations.
In the current study, the Round Bar, Surface Crack – 360 Degrees, Through-Wall Membrane and Bending Stress (KBSCL) solution was independently investigated. The primary objective was to estimate stress intensity factors using parametric, linear elastic finite element models for a generalized stress distribution. The results were used to calibrate the respective influence coefficient values for a 4th order polynomial stress field in the radial direction. The study also assessed the API 579-1 three term weight function method, commonly used for arbitrary stress distributions, for the KBSCL crack configuration. Proposed updates to the global bending solution are also included. Finally, a comparison of the newly calculated influence coefficient values to previous results by Mangard (2017) was conducted, where the results are within a few tenths of a percent.
The Influence of Secondary Damage Mechanisms on the Suitability of the Single Specimen Unloading Compliance Technique to Assess the Fracture Toughness of SA508 GR. 4N and A533B Low Alloy Steel
Authors: Cooper Adam J. , Woodward Ronnie G. , Harrison Andrew W. , Wisbey Andrew 
Published: November 2024

Abstract
In the UK, high-integrity components for new nuclear reactors are subjected to extensive fracture toughness testing (FTT) qualification programmes to ascertain their resistance to ductile fracture and justify the toughness values used in safety case arguments. One cost-effective route to delivery of such programmes is the single-specimen FTT test method, which seeks to establish a complete J-integral resistance (J-R) curve from a single-specimen by calculating the incremental J-integral with increasing crack extension. This is achieved by monitoring the change in compliance associated with incremental crack growth during testing. Importantly, it assumes that a single primary crack is generated from the tip of a pre-existing fatigue crack during fracture toughness testing, the extension of which can be directly correlated to the change in compliance of the test specimen.
The study described herein follows an investigation into the suitability of the single-specimen unloading compliance (ULC) technique for characterising the J-R fracture toughness behaviour of an A533B pressure vessel steel. By comparing to data acquired from fracture toughness testing of SA508 Gr. 4N, it is shown that high toughness, low yield strength structural materials can, despite meeting the minimum allowable specimen size requirements of ASTM E1820-23, result in secondary damage mechanisms that are thought to be driven by global plasticity and a loss of crack tip constraint. This work compliments previously reported work on linking fracture assessment methodology to fracture toughness testing procedures.
This secondary ductile damage, revealed through metallographic sectioning, extends below the fracture surface and is orientated in the primary crack plane. These secondary ductile cracks were observed to not only originate in the crack tip blunting region but also in the ductile tearing region; in some cases, secondary cracks were observed to be on the order of mm in length running parallel to the primary crack. This work shows how the presence of this secondary damage influences the compliance measurements obtained during single-specimen analysis techniques. The work also demonstrates how these secondary damage mechanisms may not be captured when using a conventional multi-specimen fracture toughness testing approach, which is often credited with being a more reliable testing methodology over single-specimen techniques.
Evaluation of the API 579-1/ASME FFS-1 KSTC Stress Intensity Factors
Authors: Altstadt Steven , Leakey Scott 
Published: November 2024

Abstract
The API 579-1/ASME FFS-1 2021 (API 579-1) Fitness-For-Service stress intensity factor solutions for a sphere with a through-wall crack (KSTC) was investigated. Finite element models of through-thickness cracked spheres subjected to uniform crack face loading, linear crack face loading, and internal pressure induced stress fields were created and used to estimate stress intensity factors (K) along the various crack fronts, which were then used to establish influence coefficient values. Due to the extreme change in K near the surface vertices it is a common practice in engineering applications to extrapolate an effective K at the inside and outside surface locations based on a curve fit of the through-wall K variation. The method of extrapolation used for this assessment is similar to WRC 478, which established the basis for spheres and other through-thickness cracked shapes in API 579-1. The parametric space includes the current space covered in API 579-1 for KSTC, plus new higher ratios of sphere internal radius to thickness. The comparison of the newly calculated stress intensity factors to the existing API 579-1 KSTC values showed good agreement in some cases and appreciable differences for the remaining cases. The differences are likely due to improved mesh refinement and choices with the post-processing curve fitting strategy for the current results. The new influence coefficient values presented herein are recommended for fitness-for-service assessments that involve KSTC.