bluuebunny/crossref_metadata_2025_split huggingface dataset:
Validation of new automated turbidimetric immunoassays for the measurement of haptoglobin and inter‐α‐trypsin inhibitor heavy chain H4 specific for the bovine species
Authors: Bassols Anna , Robles‐Guirado José Angel , Arroyo Laura , Soler Lourdes , García Natalia , Pato Raquel , Peña Raquel , Saco Yolanda , Armengol Ramon , Lampreave Fermín , Alava María A. , Canalias Francesca , Piñeiro Matilde 
Published: November 2022

AbstractBackgroundGood strategical programs are required for the early detection of disease even in the absence of evident clinical signs, which is crucial in satisfying animal welfare. Haptoglobin (Hp) and inter‐α‐trypsin inhibitor heavy chain H4 (ITIH4) are acute phase proteins and good biomarkers of early inflammation in cattle, with plasma levels that significantly increase after injury or infection.ObjectivesWe aimed to develop and validate two new immunoturbidimetric methods for Hp and ITIH4.MethodsSpecies‐specific antibodies were obtained and used to develop the immunoassays. For the Hp assay, antibodies were fixed to latex microparticles to enhance detection. The immunoassays were set up in an automated analyzer to carry out validation studies. Reference intervals were calculated using Reference Value Advisor.ResultsThe Hp immunoturbidimetric method had a linear analytical range up to 0.40 mg/mL. The limit of detection (LoD) was 0.005 mg/mL, and the limit of quantification (LoQ) was 0.007 mg/mL. Total imprecision was less than 7%. Comparison with ELISA and single radial immunodiffusion (SRID) showed good correlation, whereas the comparison with the colorimetric method showed constant and proportional differences. The ITIH4 immunoassay showed linearity up to 5 mg/mL, and the LoD was 0.002 mg/mL. Total imprecision was less than 6%. Method comparison showed a good correlation with single radial immunodiffusion, both methods being equivalent. Bilirubin, triglycerides, and hemoglobin presented no interference in any of the assays. Reference intervals were 0.007‐0.017 mg/mL for Hp and 0.2‐0.7 mg/mL for ITIH4 in dairy cows 10 days before parturition.ConclusionsImmunoturbidimetric methods developed for Hp and ITIH4 can measure basal and increased levels of these proteins, showing adequate precision, accuracy, and robustness.
Impact of Dynamic Slab Insulation on Energy Performance of Residential Buildings
Authors: Rajabi Roya , Dehwah Ammar H. A. , Krarti Moncef 
Published: November 2022

Abstract
In this paper, the energy efficiency potential of applying novel dynamic insulation systems to slab foundations is investigated for residential buildings. Specifically, dynamic insulation allows the foundation to change its thermal resistance to reduce both heating and cooling thermal loads compared to static insulation systems. The energy benefits of the dynamic insulation are evaluated using a validated numerical model integrated with a state-of-art whole-building simulation tool. Specifically, optimal settings for slab-integrated dynamic insulation are determined monthly to reduce heating and cooling thermal loads while maintaining thermal comfort for a prototypical house located in representative US climates. The analysis results indicate that the deployment of slab-integrated dynamic insulation can reduce heating energy by 10% and cooling energy by 39%, and total heating, ventilating, and air conditioning end-use by up to 12%, especially for houses located in cold climates.
Fatigue Benchmark Comparison Effort Between Code_Aster and CNNC/NPIC Software – Part 3
Authors: Liu Yin , Xie Hai , Kong Zichen , Shao Xuejiao , Courtin Stephan , Cuvilliez Sam , Xiong Furui 
Published: November 2022

Abstract
Fatigue is a phenomenon identified as a significant degradation mode which affects industrial facilities, in particulier the lifespan of nuclear power plants. As one of its important branches, the environmentally assisted fatigue (EAF) considers not only effects of unfavorable mechanical and thermal conditions, but also PWR primary water environment in nuclear components. This phenomenon can accelerate fatigue related structure failure for common materials in nuclear components such as austenitic stainless steels and nickel-based alloys.
Within this frame of reference, the RCC-M code formulated by AFCEN has included probationary phase rules named RPP-2 and RPP-3. EDF and CNNC/NPIC have hence established a specific collaboration on environmentally assisted fatigue to contribute to validation and improvement of these rules in the RCC-M code.
Part 1 of the paper states the context of the collaboration between EDF and CNNC/NPIC and the methods used by each side. Part 2 presents the satisfactory results of code comparison based on the AFCEN-provided benchmark case. As the third part, this paper presents the comparison based on an industrial case close to an HPR1000 nozzle under pressurized thermal shock (PTS) provided by CNNC/NPIC, where the RCC-M code is applied in a situation equivalent to the engineering practice.
By following the methodology of the Part 2, EDF and CNNC/NPIC use respectively their proper tools code_aster POST_RCCM and FAC_NPIC to calculate the cumulative fatigue usage factor with or without considering the effect of EAF following the comparison between RCC-M RPP and NUREG/CR-6909 rev.1. The comparison focuses on the technical details of transient combination method and temporal discretization of transients. Analysis concerning pressurized thermal shock type transients is also discussed.
Comparisons show some differences between the results of the two parts. Some could be attributed to the various calculation processes between EPRI Guidelines and RCC-M RPP-3. Minor differences could be attributed to engineering practices like thermal time stepping.
Classification Recognition of Long Distance Oil and Gas Pipeline Girth Welds MFL Signal Diagrams Based on VGG16 Network
Authors: Geng Liyuan , Dong Shaohua , Zheng Li , Li Shengwei 
Published: November 2022

Abstract
In recent years, with the development of long-distance oil and gas pipelines, the number of accidents, most of which caused serious consequences, is increasing gradually. According to statistics, pipeline cracking caused by girth weld problems accounts for a large proportion of all. Girth weld defects of long-distance oil and gas pipelines, such as cracks, incomplete fusion and incomplete penetration, seriously threaten the safety of pipelines. Because the internal magnetic flux leakage detection (MFL) signal is complex at the girth weld, it is difficult to judge the defect type through conventional data analysis. In this paper, MFL signal screenshots of girth welds, which are automatically captured from MFL client software by the Python program, are the training sample set of VGG16. This training sample set which includes 1396 samples labeled with radiographic test results after girth welds excavation, is divided into three categories: qualified samples, unqualified samples with circular/strip defects, and unqualified sample with crack/incomplete fusion/incomplete penetration defects. The deep learning network after training is used to predict the classification of 156 test samples, and the prediction accuracy is 78%. This method can effectively judge whether there are hazardous girth weld defects types, which are significant for safety management of long-distance oil and gas pipeline girth welds.
Evaluation of Validity Criteria for Subsize Compact Tension Specimens Using a Bending Modified J-A2 Solution
Authors: Bagnoli Kenneth , Thorwald Greg , Holloman Ryan , Hioe Y. 
Published: November 2022

Abstract
Many existing pieces of plant equipment do not have original impact test data or suffer from a loss in toughness over time. As a result, the ability to remove material for testing can be of significant value. Often, extraction of sufficient material for conducting fracture toughness testing necessitates weld repair to fill in the sample location. Some equipment may also require stress relief. Use of subsize test specimens that minimizes the amount of material removed can permit local thin area acceptance criteria to be met and avoids weld repair in most cases. However, for subsize specimens that are substantially smaller than conventional geometries, it is important to examine the limits within which a valid J integral can be measured when tests display significant amount of ductility. Standards like ASTM E1820-20 provide restrictions on the maximum J integral (Jmax) based on specimen thickness (B), uncracked ligament length (bo) as well as maximum crack growth Δa. These limits ensure the stress-strain fields at the crack tip are well described by J, a condition referred to as J dominance. In the first phase of this project, detailed 3D FEA analyses of subsize compact tension C(T) specimens (commonly called mini-CT) have been performed to explore the criteria necessary to obtain a valid measurement of J. This is generally considered to be a function of the materials hardening exponent, mode of loading, and the specimen dimensions. One methodology to examine if J controlled crack growth exists is to evaluate the crack tip stress field, and compare this to the theoretical HRR solution. In the case of the mini-CT, due to limitations associated with the small specimen size and extent of yielding across the uncracked ligament, the two parameter J-A2 solution was used to extend the range of J dominance. Additional modification of J-A2 is made by accounting for the effect of global bending on crack tip opening stress (J-A2-M) following the procedures developed by Zhu et al. [1] and Chao et al. [2] for SEN(B) specimens. The results of this study indicate that Jmax for the mini-CT may be given as Jmax&lt;(Bn,bo)σo5 for typical pressure vessel steels. Where Bn is the specimen net thickness, bo is the ligament length and σo is the yield stress. However, test results as well as consideration for plastic collapse suggest that while a valid measurement of initiation J (Ji) may be possible, the extent of J controlled crack growth is more restrictive than the ASTM E 1820-20 limit of Δa = 0.25bo, and may be closer to 0.08 bo.
Extrapolation of High Temperature Material Properties of Inconel 617 for Molten Chloride Reactor Experiment Applications
Authors: Rajasekaran Ramesh , Ching Hsu-Kuang , Deleo Francesco 
Published: November 2022

Abstract
The Inconel 617 material was developed in the early 1970’s for high-temperature applications. It is a nickel-chromium-cobalt-molybdenum alloy with high strength combined with corrosion and oxidation resistance properties. Inconel 617 is one of the contenders for the Reactor Enclosure System (RXE) material of the Molten Chloride Reactor Experiment (MCRE). The properties of Inconel 617 are not available in the high temperature code ASME Boiler & Pressure Vessel Code (BPVC) Section III, Division 5 [1] but are given in Code Case N-898 [2]. However, for Inconel 617, the high temperature properties (stress to rupture and isochronous stress-strain curves) are available only up to 100,000 hours unlike stainless steels (SS) 304 and 316 for which properties are available for a time up to 300,000 hours. Consequently, the analyst must use 100,000 hours as the maximum creep life even for a very low stress value adding more conservatism to the already conservative elastic route of creep-fatigue lifing. This in turn limits the maximum operating temperature when the design curves are plotted. The purpose of this work is to identify a methodology to extrapolate the high temperature properties of Inconel 617 up to 300,000 hours. The two properties that need extrapolation are a) time to rupture and b) isochronous stress-strain behavior.
This work shows that for the time to rupture calculation, extrapolation of properties using the last two data points looks appropriate when evaluated against the Larson-Miller Parameter method [4]. For isochronous stress-strain curves, the same equations given in the ASME code case [2] can be extended up to 300,000 hours.
Technical Basis of ASME B31 Code Case 216: Use of Enhanced Pressure Ratings for Brazed Copper Tubes and Fittings by Cold Stretch Process
Authors: Xu Kang , Timoteo Gustavo , Renaldo Adam , Miller Philip , Wills Terry 
Published: November 2022

Abstract
Copper tubes and fittings are widely used in the industrial gas industry because of their outstanding cryogenic properties, high toughness, and easy installation. However, one notable disadvantage of the copper materials is their low allowable stresses and hence low-pressure rating in the annealed condition. ASME B31 Code Case 216 has been developed to overcome this shortcoming. The Code Case provides detailed design and construction procedures for copper tubes and fittings and permits significantly enhanced pressure rating with no compromise in B31.3 design safety factor. This paper documents the technical details of the Code Case development. By taking advantage of excellent work hardening and toughness properties, especially at cryogenic temperatures, it was demonstrated that a significant increase in allowable stress can be obtained for copper tubes after a small amount of cold work. The work hardening is achieved by a carefully controlled cold stretch operation simultaneously done during the pressure test. Through extensive destructive testing, it was shown that the pressure rating of the copper tubes and fittings can be safely increased more than 60% compared with traditional B31.3 designs. Additional limitations and safety precautions are also discussed when applying this Code Case.
Revision of Case N-666-1 to Permit Overlay Repair of Dissimilar Metal Socket Welds and to Allow Higher Carbon Content in the Pipe and Socket Fitting
Authors: McCracken Steven L. , Lohse Christopher 
Published: November 2022

Abstract
ASME Section XI Case N-666, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, was developed for repair of non-isolable leaking socket welds where the mode of failure is determined to be fatigue cracking attributed to mechanical vibration [1]. The case was approved by ASME on July 23, 2002 and first published in the 2004 Code Cases: Nuclear Components, Supplement 9.
Case N-666 and N-666-1 have served the industry well, allowing repair of leaking socket welds where the system cannot be readily drained and isolated for cutout and full pipe replacement. This has provided significant benefit to the nuclear industry by allowing the repair to be performed online without the need to shut the plant down, avoiding significant loss in power generation.
This paper provides the technical basis for proposed changes to Case N-666-1 that will expand the scope of socket welds that can be repair by weld overlay. The revision will expand the case to include overlay repair of dissimilar metal socket welded joints and will remove the 0.30 wt% maximum carbon content limitation when the overlay repair is installed with water backing. Finally, the revision will also address the conditions imposed by the NRC in Regulatory Guide 1.147 Revision 19.
BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2
Authors: Arffman Pentti , Lydman Jari , Hytönen Noora , Que Zaiqing , Lindqvist Sebastian 
Published: November 2022

Abstract
Project BRUTE has investigated weld materials extracted from the decommissioned Barsebäck 2 reactor pressure vessel. The materials investigated originate from the pressure vessel head (RPVH) and beltline regions. The performed mechanical testing include tensile, Charpy impact and fracture toughness testing.
Tensile testing with miniature specimens demonstrates a difference of over 50 MPa in the yield and ultimate tensile strengths of the RPVH and beltline materials. Beltline specimens tested at the operating temperature exhibit discontinuity past the yield region, possibly indicating dynamic strain aging.
Charpy impact tests were performed around the transition region of the material. Transition curves were fitted, and reference temperatures T28J of −85 °C and −106 °C were determined for RPVH and beltline materials, respectively. This indicates better material properties at beltline compared to the RPVH, in agreement with tensile results. The reference temperatures T28J were further utilized to estimate brittle fracture initiation toughness reference temperatures T0.
Fracture toughness testing follows the Master Curve methodology defined in ASTM standard E1921. Reference temperatures T0 were determined at −115.1 °C and −101.1 °C for the RPVH and beltline, respectively, but the tests indicate inhomogeneity in both materials. The mean reference temperatures of the multimodal models TM were determined at −110.0 °C and −96.5 °C, and the associated, margin adjusted lower confidence bounds TM5%, MA at −13.3 °C and −53.0 °C for the RPVH and beltline materials, respectively. The latter values indicate that the inhomogeneity is more extensive in the RPVH. The estimates obtained from the Charpy impact toughness results do not correlate consistently with the fracture toughness-based transition temperature, possibly due to the inhomogeneity of the materials.
The results show that the safety of the materials can be assessed reliably, provided that contemporary methods, equipment and analyses are used.
FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins
Authors: Brynk Tomasz , Uytdenhouwen Inge , Arffman Pentti , Altstadt Eberhard , Kopriva Radim , Obermeier Florian , Serrano Marta 
Published: November 2022

Abstract
The H2020 FRACTESUS project is aimed at the validation of miniaturized compact tension (MCT) specimen. More specifically the usage of the MCT with the Master Curve (MC) oriented fracture toughness testing of reactor pressure vessel (RPV) materials in hot cell conditions will be examined. In the first stage of the project, a general strategy of material selection and testing processes has been established. The choice of the selected RPV materials is based on the widest possible range of mechanical properties expected for baseline materials, but also resulting from their exposure to neutron irradiation, in terms of different MC reference temperature T0, and properties determined from Charpy impact testing. Moreover, in order to validate the use of the MCT in a broad application space, it was decided to perform FT tests for both base metals and welds. The largest challenge was related to the availability of those materials. They need to be tested in numerous, planned round robin exercises. They should have already an existing extensive database of fracture toughness results obtained using large specimens. The final version of the test matrix was prepared, keeping all those requirements in mind. An irradiated round robin exercise is planned for one type of weld material, namely 73W, that will be tested by seven partners. Additionally, the FRACTESUS partners were divided into smaller groups with 3–5 participants who will test a sub-selection of unirradiated materials in six round robin exercises. This paper presents the summary of the material selection activities in the FRACTESUS project. The materials are briefly described and rationale for their usage within the project is provided.
Root Cause Failure Investigation of MSCV Drain Failures
Authors: Jackson Peter , Wholey Alex , Tsai Eric , Burns Darby 
Published: November 2022

Abstract
Main Steam Stop and Control Valves (MSCVs) are safety critical components in modern steam power plants including large, combined cycle gas turbine (CCGT) plants. Repeated failures of the after seat drain piping at a dissimilar metal weld have occurred at one large CCGT that is regulated by the ISO in AGC and therefore experiences few startups.
This paper describes the results from a comprehensive evaluation of contributors to the repeated failures in one of two MSCV including: pipe stress analysis of the drain pipe layout, vibration testing of the MSCV and drain piping system using accelerometers and motion amplified video (MAV) technology and other inspections of the large bore pipe hanger system adjacent to the valves.
Forensic investigations by a metallographic laboratory were conducted which provide important conclusions about the root cause of the drain weld failures, material condition and heat treatment procedures. Additional calculations of transient thermal stress were also conducted in accordance with the guidance that is available in ASME Code Section III NB-3650 to address additional stress that is present due to transient temperature conditions at the failed DMW weld where a substantial geometric discontinuity is present between the drain pipe and the downstream forged block valve.
Results from plant operating data archives were used to establish process conditions during plant startup and indexing the measured vibration characteristics when the MSCV drains opened and closed. Field NDT (PMI, UT thickness testing) and hardness testing was used to confirm the material in the drain lines components which have not experienced failures.
Recommendations were developed from this program that identify the principal cause of the high level of vibration in the affected MSCV, the benefits of modifications to the drain system pipe materials, dimension and layout and the improvement of oversight of heat treatment of future repairs.
Friction Stir Welding of Hybrid Recycled Metal Matrix Composites
Authors: Christy John Victor , Ismail Mourad Abdel Hamid 
Published: November 2022

Abstract
In this work, conventional Friction Stir Welding (FSW) was used to investigate the weldability of recycled hybrid Aluminum Matrix Composites (AMCs). The novel composites were developed by squeeze stir casting process of scrap aluminum alloy wheels of cars as matrix and 4 wt.% of graphite, and 5 wt% of alumina as reinforcements. The casting parameters optimized from our previous work, such as squeeze pressure of 100 MPa, squeeze time of 45s, die preheating temperature of 250°C, and stirrer speed of 525 rpm, were used while casting the hybrid AMC rods. 4 mm plates were cut from each rod and subjected to an in-air friction stir welding process using a cylindrical tool of 16 mm diameter and 3 mm pin depth. Two-pass welding with a tool rotation of 1600 rpm and feed rates of 24 mm/min and 55 mm/min were used for FSW of samples. The welded section was cut out and subjected to mechanical tests such as tensile and Brinell hardness tests. It was observed that the samples welded at lower feed rates exhibited a higher tensile strength of 154 MPa and Brinell Hardness number of 61. The weldability of the recycled composites was successfully tested using FSW, a sustainable welding process. The work shows that hybrid recycled AMCs can be used for piping’s and structures prone to wear.