bluuebunny/crossref_metadata_2025_split huggingface dataset:
Investigating the Correlation Between Different Effective Stress Measures and the Service Life of Actual High-Temperature Structural Components
Authors: Rovinelli Andrea , Messner Mark C. , Sham T.-L. 
Published: December 2020

Abstract
Effective stress measures are utilized by engineers to correlate uniaxial and biaxial experimental rupture data to creep failure in real components. Different effective stress formulations are used in various high temperature design codes, such as the Section III Division 5 of the ASME Boiler and Pressure Vessel code and the French RCC-MRx, and in different fitness for service provisions, such as the British R5 and the American FFS-1. Under uniaxial and biaxial stress states all the investigate metrics predict similar rupture times and provide similar safety margins, however there is no guarantee that when these metrics are extrapolated to predict the creep life for triaxial state they will remain conservative. In this work we use the real geometry of a Grade 91 end-plate that failed prematurely and finite element simulations to investigate the variability in creep life predictions obtained utilizing different effective stress as creep-damage driving force. Results show that for triaxial stress states the time to crack nucleation, the crack initiation site and the crack path are extremely sensitive to the effective stress measure.
Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components
Authors: Barua B. , Messner M. C. , Jetter R. I. , Sham T.-L. 
Published: December 2020

Abstract
The clad selection criteria proposed in this work supports a design approach provided in [PVP2020-21469] for cladded component for high temperature nuclear service. The proposed design method guards the clad material against the creep-fatigue failure and ratcheting strain accumulation in elevated temperature nuclear service without the requirement of long-term material properties. However, it limits the type of clad materials that can be used with the existing Class A materials qualified for ASME Section III, Division 5 rules. The analysis approach and design rules allow the use of two types of clad materials — soft clads that creep much faster than the base material and hard clads that creep much slower and have higher yield stress than the base material. This work proposes selection criteria for such soft and hard clad materials to use with a Class A metallic alloy — austenitic steel 316H. The criteria are developed based on the effect of relative elastic modulus and creep rate on the long term stress redistribution between the 316H base and the clad material. The proposed clad selection criteria are applicable up to a design temperature of 750°C and for 1% to 10% thick cladding. The selection criteria are evaluated on two materials — nickel and a molybdenum based alloy TZM — categorizing them as soft or hard clad for 316H base material.
Codes, Standards, Rules and Assumptions on Environment Assisted Fatigue for Fatigue Management of Primary Piping
Authors: Solin Jussi , Seppänen Tommi , Vanninen Rami , Pulkkinen Erkki , Lemettinen Petri , Faidy Claude 
Published: December 2020

Abstract
All international codes used for design, operation and inspection of NPP primary circuit pressure boundaries are rooted to the ASME Boiler and Pressure Vessel Code, Section III, Nuclear Vessels, 1963. Article 4, N-415 “Analysis for cyclic operation” instructed calculation of stress intensities for fatigue transients and provided two design curves for basic material types. Different codes such as ASME, RCC-M, KTA, PNAE and JSME have much in common, but partial deviations exist.
In 2007 the US NRC Regulatory Guide 1.207 endorsed a methodology for accounting the environmental effects. It was mainly based on extensive work in Japan and the Argonne National Laboratory. The final report of ANL, NUREG/CR-6909 became a major reference and subject of criticism. However, the first approach for environment assisted fatigue (EAF) written in ‘code language’ was published in Japan and a regulatory requirement for consideration of EAF both for operating reactors and new designs appeared first in Finland.
This paper discusses challenges in management of fatigue and the evolving state-of-the-art in different codes, standards, rules and assumptions. The roots and current status of fatigue curves and design criteria applied in Finnish NPP’s are explained.
Evaluation of Mean Stress Correction on Fatigue Curves of Grade 91 and Alloy 617 in ASME Section III Division 5
Authors: Wang Y. , McMurtrey M. D. , Jetter R. I. , Sham T.-L. 
Published: December 2020

Abstract
The current ASME Boiler and Pressure Vessel (B&PV) Code Section III, Division 5, Subsection HB, Subpart B has only one design fatigue curve for grade 91 steel (Gr. 91) at 540 °C (or 1000 °F). The ASME Section III Working Group on Creep-Fatigue and Negligible Creep (WG-CFNC) has taken an action to incorporate the temperature-dependent design fatigue curves for Gr. 91 developed by Japan Society of Mechanical Engineers (JSME) into ASME Section III Division 5. During the process, issues regarding the effect of mean stress on fatigue analysis, and how to consider the mean stress effect for elevated-temperature design, were brought up. To evaluate whether the design fatigue curves of Gr. 91 needed adjustment to account for mean stress, critical tests were designed and performed at 371 °C (700 °F) and 540 °C (1000 °F). This study is similar to the work performed on Alloy 617 when its fatigue design curves were established for temperature range of 538–704°C (1000–1300°F) as part of the Code Case package for Alloy 617 to be used as Class A construction material in Division 5. The effects of mean stress on Alloy 617 were evaluated at 550°C (1022°F). The results showed that the mean stresses introduced by the non-zero mean strain could not be maintained under strain-controlled fatigue and resulted in negligible effect on the fatigue life. Mean stress correction was not recommended for Alloy 617 fatigue design curves in Division 5. This study shows the same conclusion for Gr. 91.
The Impact of Geometric Discontinuities on Alloy 617 Creep-Rupture Behavior
Authors: Rupp Ryann E. , McMurtrey Michael D. 
Published: December 2020

Abstract
The Nuclear Regulatory Commission (NRC) is currently reviewing Section III, Division 5 of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for potential endorsement. A prior NRC-sponsored review on the application of Section III, Division 5 design rules for elevated-temperature reactors have identified issues currently not in the code that need to be addressed. These include an insufficient knowledge of the effect of notches, structural discontinuities, and multiaxial stress. This work qualitatively evaluates Alloy 617 as notch strengthening or notch weakening and investigates the impact of multiaxial stress on Alloy 617 creep behavior.
Multiaxial stress does not degrade Alloy 617’s short-term creep-rupture properties. This was concluded from the following observations: 1) multiaxial creep resided on or to the right of the Larson-Miller curve for uniaxial creep-rupture data, 2) Alloy 617 exhibited notch strengthening, and 3) creep-rupture life increased with a stronger multiaxial stress. Long-term and intermediate creep-rupture tests are in progress in order to determine whether notch behavior will cross from strengthening to weakening at lower stresses and longer rupture lifetimes. A nondestructive characterization methodology using X-ray computed tomography is explored as a means to identify the failure location on the specimen prior to rupture.
Background on Low Temperature Overpressure Protection System Setpoints for Pressure-Temperature Curves
Authors: Poehler Jeffrey C. , Stevens Gary L. , Udyawar Anees A. , Freed Amy 
Published: December 2020

Abstract
ASME Code, Section XI, Nonmandatory Appendix G (ASME-G) provides a methodology for determining pressure and temperature (P-T) limits to prevent non-ductile failure of nuclear reactor pressure vessels (RPVs).
Low-Temperature Overpressure Protection (LTOP) refers to systems in nuclear power plants that are designed to prevent inadvertent challenges to the established P-T limits due to operational events such as unexpected mass or temperature additions to the reactor coolant system (RCS). These systems were generally added to commercial nuclear power plants in the 1970s and 1980s to address regulatory concerns related to LTOP events. LTOP systems typically limit the allowable system pressure to below a certain value during plant operation below the LTOP system enabling temperature.
Major overpressurization of the RCS, if combined with a critical size crack, could result in a brittle failure of the RPV. Failure of the RPV could make it impossible to provide adequate coolant to the reactor core and result in a major core damage or core melt accident. This issue affected the design and operation of all pressurized water reactors (PWRs).
This paper provides a description of an investigation and technical evaluation regarding LTOP setpoints that was performed to review the basis of ASME-G, Paragraph G-2215, “Allowable Pressure,” which includes provisions to address pressure and temperature limitations in the development of P-T curves that incorporate LTOP limits. First, high-level summaries of the LTOP issue and its resolution are provided. LTOP was a significant issue for pressurized water reactors (PWRs) starting in the 1970s, and there are many reports available within the U.S. Nuclear Regulatory Commission’s (NRC’s) documentation system for this topic, including Information Notices, Generic Letters, and NUREGs. Second, a particular aspect of LTOP as related to ASME-G requirements for LTOP is discussed. Lastly, a basis is provided to update Appendix G-2215 to state that LTOP setpoints are based on isothermal (steady-state) conditions.
This paper was developed as part of a larger effort to document the technical bases behind ASME-G.
Technical Basis for Revision to ASME Section XI Appendix C for Stress Corrosion Crack Growth Rate Equations for Alloy 600 and Associated Welds
Authors: Jenks Amanda , Bamford Warren H. 
Published: December 2020

Abstract
Alloy 600 and its associated weld metals (Alloys 82, 182, and 132) have been used extensively for nuclear power plant construction. These alloys are known to be susceptible to primary water stress corrosion cracking (PWSCC), and reference crack growth rate (CGR) equations for this degradation mechanism were first incorporated into the ASME Boiler and Pressure Vessel Code in the 2009 Addenda of the 2007 Edition via Section XI, Nonmandatory Appendix C. These original equations were developed from a large dataset to which numerous international laboratories contributed. It was reviewed and assessed by an Expert Panel. In 2015, another Expert Panel was organized, including members from the original Expert Panel. Publicly available data produced since the first equations were developed, and data that had not been part of the original model development process, were collected. The data were screened for testing quality and plant applicability by the Expert Panel, and new PWSCC equations were developed. This paper summarizes the development of the revised PWSCC equations for Alloy 600 and Alloy 82/182/132 to support revision of the equations previously incorporated into Appendix C of ASME B&PV Code Section XI.
Analysis of HDPE Failure Data in Support of Development of Flaw Acceptance Criteria for Butt Fusion Joints
Authors: Liu Cheng , Scarth Douglas , Munson Douglas P. , Wolfe Ryan 
Published: December 2020

Abstract
There is a need for ASME B&PV Code procedures and acceptance criteria for evaluation of flaws detected by inspection of high density polyethylene (HDPE) piping items in safety Class 3 systems. To support the development of flaw acceptance criteria for butt fusion joints in HDPE pipes, a series of coupon tests have been completed for specimens cut from butt fused HDPE pipes with surface or subsurface flaws placed in the joints prior to fusion process. Specimens containing known flaw sizes were tested under axial load at accelerated stresses and temperatures until failure; or until a prescribed number of test hours was reached. The failure time from the tests has been correlated to the net section stress and the stress intensity factor, and the results showed that the failure time can be better represented by the stress intensity factor. The test results were then used to fit the Brown and Lu formula that predicts the time to failure due to the slow crack growth of flaws as a function of stress intensity factor and temperature. With the developed Brown and Lu equation, the allowable stress intensity factors for a piping lifetime of 50 years at the maximum code allowable temperature of 60°C have been proposed for both surface and subsurface flaws in HDPE butt fusion joints. Examples of what might be corresponding allowable flaw sizes in the butt fusion joints of piping are also provided.
Fatigue Consideration of Layered Vessels
Authors: Xu Kang , Rana Mahendra , Jawad Maan 
Published: December 2020

Abstract
Layered pressure vessels provide a cost-effective solution for high pressure gas storage. Several types of designs and constructions of layered pressure vessels are included in ASME BPV Section VIII Division 1, Division 2 and Division 3. Compared with conventional pressure vessels, there are two unique features in layered construction that may affect the structural integrity of the layered vessels especially in cyclic service: (1) Gaps may exist between the layers due to fabrication tolerances and an excessive gap height introduces additional stresses in the shell that need to be considered in design. The ASME Codes provide rules on the maximum permissible number and size of these gaps. The fatigue life of the vessel may be governed by the gap height due to the additional bending stress. The rules on gap height requirements have been updated recently in Section VIII Division 2. (2) ASME code rules require vent holes in the layers to detect leaks from inner shell and to prevent pressure buildup between the layers. The fatigue life may be limited by the presence of stress concentration at vent holes. This paper reviews the background of the recent code update and presents the technical basis of the fatigue design and maximum permissible gap height calculations. Discussions are made in design and fabrication to improve the fatigue life of layered pressure vessels in cyclic service.
Late onset depression: dopaminergic deficit and clinical features of prodromal Parkinson’s disease: a cross-sectional study
Authors: Kazmi Hiba , Walker Zuzana , Booij Jan , Khan Faraan , Shah Sachit , Sudre Carole H , Buckman Joshua E.J. , Schrag Anette-Eleonore 
Published: December 2020

BackgroundLate onset depression (LOD) may precede the diagnosis of Parkinson’s disease (PD) or dementia with Lewy bodies (DLB). We aimed to determine the rate of clinical and imaging features associated with prodromal PD/DLB in patients with LOD.MethodsIn a cross-sectional design, 36 patients with first onset of a depressive disorder (Diagnostic and Statistical Manual of Mental Disorders IV criteria) diagnosed after the age of 55 (LOD group) and 30 healthy controls (HC) underwent a detailed clinical assessment. In addition, 28/36 patients with LOD and 20/30 HC underwent a head MRI and 29/36 and 25/30, respectively, had dopamine transporter imaging by 123I-ioflupane single-photon emission computed tomography (SPECT) imaging. Image analysis of both scans was performed by a rater blind to the participant group. Results of clinical assessments and imaging results were compared between the two groups.ResultsPatients with LOD (n=36) had significantly worse scores than HC (n=30) on the PD screening questionnaire (mean (SD) 1.8 (1.9) vs 0.8 (1.2); p=0.01), Movement Disorder Society Unified Parkinson’s Disease Rating Scale total (mean (SD) 19.2 (12.7) vs 6.1 (5.7); p<0.001), REM-sleep behaviour disorder screening questionnaire (mean (SD) 4.3 (3.2) vs 2.1 (2.1); p=0.001), Lille Apathy Rating Scale (mean (SD) −23.3 (9.6) vs −27.0 (4.7); p=0.04) and the Scales for Outcomes in PD-Autonomic (mean (SD) 14.9 (8.7) vs 7.7 (4.9); p<0.001). Twenty-four per cent of patients with LOD versus 4% HC had an abnormal 123I-ioflupane SPECT scan (p=0.04).ConclusionsLOD is associated with increased rates of motor and non-motor features of PD/DLB and of abnormal 123I-ioflupane SPECTs. These results suggest that patients with LOD should be considered at increased risk of PD/DLB.
CHARACTERIZATION OF ELECTRODEPOSITED ZIRCONIA MODIFIED NiCoCrAlY COMPOSITE COATINGS ISOTHERMALLY OXIDIZED AT 1000∘C
Authors: SRIVASTAVA MEENU , CHAUDHURI ATANU , BERA PARTHASARATHI , RAVISANKAR B. , BALARAJU J. N. 
Published: December 2020

The objective of this study is to evaluate the electrodeposited zirconia (ZrO2)-modified NiCoCrAlY composite coatings subjected to isothermal oxidation at 1000∘C under atmospheric conditions for 24 h. NiCoCrAlY composite coatings with 0, 10, 40, and 60[Formula: see text]wt.% of cobalt contents have been compared. The oxidation studies have revealed that the doping of yttrium (Y) and ZrO2 results in a significant reduction in weight gain, thereby imparting improved oxidation resistance. The morphology of the oxides formed on the surface is analyzed using field emission scanning electron microscope and the phases are identified by X-ray diffraction studies. The major oxidation products formed on the surface of NiCrAlY and Ni10CoCrAlY coatings consist of NiO. In contrast, the surface of Ni40CoCrAlY coating comprises of predominantly CoO and small amount of NiCo2O4. Cobalt oxide (CoO) is formed as the major phase on the surface of the Ni60CoCrAlY coating. The grains on the surface of ZrO2-modified NiCoCrAlY composites are faceted, while such grains are not seen in the case of unmodified coatings. The texture analysis reveals that cooling rate is the deciding factor for the facet formation. The coatings have been characterized extensively using X-ray photoelectron spectroscopy to get in-depth understanding.
A Case for Grace? Case-Grammar, Frame-Semantics, and Biblical Hebrew חֵן
Authors: Ziegert Carsten 
Published: December 2020

Abstract
The traditional rendering “grace” for חֵן is controversial. Frame semantics, a theory originating in cognitive linguistics, anticipates that prototypical situations are evoked in language users’ minds each time a word is used. Thus, a “frame” for “חֵן situations” is reconstructed from Biblical texts. Apart from the basic meaning “beauty” which is offered in dictionaries, too, an extended meaning is presented: חֵן designates “the settling of a (potential) conflict between two parties that only one party can bring to a conclusion.”
Incidence of Posterior Shoulder Instability in the United States Military: Demographic Considerations From a High-Risk Population
Authors: Bokshan Steven L. , Kotchman Halle M. , Li Lambert T. , DeFroda Steven F. , Cameron Kenneth L. , Owens Brett D. 
Published: December 2020

Background: Relatively little is known about the true incidence of posterior shoulder instability in the United States. Purpose/Hypothesis: The purpose of this study was to characterize the incidence of posterior shoulder instability in the US military population and to examine which characteristics place these patients at highest risk. We hypothesized that the rate of posterior instability in this cohort of patients would be higher than previously reported. Study Design: Descriptive epidemiology study. Methods: All initial cases of posterior shoulder dislocation and subluxation in the Defense Medical Epidemiology Database were screened between 2016 and 2018 using the relevant International Classification of Diseases–Tenth Revision-Clinical Modification codes. Incidences were calculated, and multivariate Poisson regression was used to calculate adjusted rate ratios for the effects of sex, race, age, military service branch, rank, and year. Results: The overall unadjusted incidence was 0.032 per 1000 person-years for posterior dislocations, 0.064 per 1000 person-years for posterior subluxations, and 0.096 per 1000 person-years for all cases of posterior shoulder instability. The total incidence of all shoulder instability was 1.84 per 1000 person-years, with posterior shoulder instability accounting for 5.2% of total cases. For posterior subluxation, significant differences between groups were found in the unadjusted and adjusted rate ratio (ARR) for sex (ARR, 3.31; 95% CI, 1.85-5.93 for men), race (ARR, 0.458; 95% CI, 0.294-0.714 for Black servicemembers and ARR, 0.632; 95% CI, 0.421-0.948 for servicemembers of other race), age (ARR, 3.69; 95% CI, 1.56-8.70 for patients aged 30-34 years), and military service branch (ARR, 0.663; 95% CI, 0.460-0.955 for Air Force servicemembers). For posterior shoulder dislocations, a significant difference was found only between men and women (ARR, 4.55; 95% CI, 1.85-11.2 for men). Conclusion: The incidence of posterior shoulder instability among US military personnel is higher than previously reported in the general US population, with a majority of cases due to subluxation. This increased incidence is likely reflective of a young and highly active population along with improvements in awareness and diagnosis of posterior instability in recent years.
Psychodermatology in Canada: A National Survey Assessment of Dermatologists’ Perception, Practice Patterns, and Challenges
Authors: Turk Tarek , Fujiwara Esther , Abba-Aji Adam , Mathura Pamela , Dytoc Marlene 
Published: December 2020

Objectives We aimed to assess the perception of psychodermatology, practice patterns, and challenges reported by Canadian dermatologists. Methods We designed an online questionnaire based on previous literature, including questions about practitioners’ perceptions, practice patterns, training, and challenges in psychodermatology. We solicited their opinions on desired training, research needs, and clinical approach recommendations. Our survey was distributed nationally by the Canadian Dermatology Association (CDA). Results Of the total of 78 participating dermatologists, >75% reported treating patients with psychodermatological conditions, with higher frequencies of secondary than primary psychodermatological conditions. While practitioners had some confidence in their understanding of psychodermatology (median = 4 on a 5-point scale), their comfort levels to approach these patients were lower (median = 3), and their confidence in prescribing psychotropic medication was markedly low (median = 2). A total of 50% reported that a “multidisciplinary approach” would be best for these patients. Poor access to psychiatry was the most reported (26.9%) challenge, together with time constraints, lack of training, poor communication with patients, and lack of patient insight and resources. While 46.2% reported having never participated in psychodermatology training, 55.1% expressed interest in doing so. Conclusion We identified several challenges with knowledge, awareness, and healthcare delivery in psychodermatological practice in Canada. Increasing dermatologists’ access to psychiatric consultations/services, a multidisciplinary approach with dermatologists and psychiatrists co-providing care, and more specialized training in this area are recommended to narrow the identified gaps.