bluuebunny/crossref_metadata_2025_split huggingface dataset:
Is there a role for childhood vaccination against COVID‐19?
Authors: Eberhardt Christiane Sigrid , Siegrist Claire‐Anne 
Published: October 2020

AbstractTremendous efforts are undertaken to quickly develop COVID‐19 vaccines that protect vulnerable individuals from severe disease and thereby limit the health and socioeconomic impacts of the pandemic. Potential candidates are tested in adult populations, and questions arise of whether COVID‐19 vaccination should be implemented in children. Compared to adults, the incidence and disease severity of COVID‐19 are low in children, and despite their infectiveness, their role in disease propagation is limited. Therefore, COVID‐19 vaccines will need to have fully demonstrated safety and efficacy in preventing not only complications but transmission to justify childhood vaccination. This work summarizes currently tested vaccine platforms and debates practical and ethical considerations for their potential use in children. It also discusses the already deleterious effect of the pandemic on routine childhood vaccine coverage, calling for action to limit the risks for a rise in vaccine‐preventable diseases.
The impact of COVID‐19 on the hospice and palliative care workforce
Authors: Kates Jeannette , Gerolamo Angela , Pogorzelska‐Maziarz Monika 
Published: October 2020

AbstractObjectiveTo understand the impact of the COVID‐19 pandemic on the hospice and palliative workforce and service delivery.Design and sampleThis was a cross‐sectional survey of 36 hospice and palliative care workforce members representing all United States geographic regions.ResultsMost respondents (70%) reported an increase in specific palliative care services as a result of the pandemic. Two thirds (78%) of respondents reported their agency has cared for confirmed COVID‐19 patients. Only half reported the agency had access to laboratory facilities for surveillance and detection of outbreaks in both patients and staff (58%) and that the agency could test patients and providers for COVID‐19 (55%). Qualitative comments described the impact of the pandemic and resulting social distancing measures on the emotional well‐being of patients, families, and staff.ConclusionsOur findings suggest that the COVID‐19 pandemic has strained the palliative and hospice care workforce as it provides increased services at an unprecedented rate to patients and families. The implications of these findings are important for public health nurses who are skilled in disaster management and quickly responding to emergencies. The expertise of public health nurses can be leveraged to support palliative care agencies as they strive to manage the pandemic in the communities they serve.
Governments and Formal Institutions Shaping the Networks of Co‐Production in the Chinese and German Film Industries
Authors: Xin Xiaorui , Mossig Ivo 
Published: October 2020

AbstractStudies in economic geography on the film industry often focus on the impact of social relationships and informal institutions, like habits, norms and conventions. However, the role of formal institutions has so far received only little attention. To exemplify the role of governments and formal institutions shaping the film production networks a social network analysis is carried out. The results essentially show three patterns of interventions: Firstly, governments are active players within the networks through state‐owned or public film production companies. Secondly, (especially in the case of China) governments act as regulators through formal institutions by restricting market access for international films and at the same time enabling the rapid market growth of the Chinese film market through opening policies after 2002. Thirdly, they act as promoters through direct financial means (e.g. public film subsidies in Germany) or through support measures by the cultural and creative industries in general.
The floral repressors TEMPRANILLO1 and 2 modulate salt tolerance by regulating hormonal components and photo‐protection in Arabidopsis
Authors: Osnato Michela , Cereijo Unai , Sala Jan , Matías‐Hernández Luis , Aguilar‐Jaramillo Andrea E. , Rodríguez‐Goberna María Rosa , Riechmann José Luis , Rodríguez‐Concepción Manuel , Pelaz Soraya 
Published: October 2020

SUMMARYMembers of the plant specific RAV family of transcription factors regulate several developmental and physiological processes. In the model plant Arabidopsis thaliana, the RAV TEMPRANILLO 1 (TEM1) and TEM2 control important phase changes such as the juvenile to adult and the vegetative to reproductive transitions. Besides their known regulatory function in plant development, a transcriptomics analysis of transgenic plants overexpressing TEM1 also revealed overrepresentation of Gene Ontology (GO) categories related to abiotic stress responses. Therefore, to investigate the biological relevance of these TEM‐dependent transcriptomic changes and elucidate whether TEMs contribute to the modulation of plant growth in response to salinity, we analyzed the behavior of TEM gain and loss of function mutants subjected to mild and high salt stresses at different development stages. With respect to increasing salinity, TEM overexpressing plants were hypersensitive whereas the tem1 tem2 double mutants were more tolerant. Precisely, tem1 tem2 mutants germinated and flowered faster than the wild‐type plants under salt stress conditions. Also, tem1 tem2 plants showed a delay in salt‐induced leaf senescence, possibly as a consequence of downregulation of jasmonic acid biosynthesis genes. Besides a shorter life cycle and delayed senescence, tem1 tem2 mutants appeared to be better suited to withstand oxidative stress as they accumulated higher levels of α‐tocopherol (an important antioxidant metabolite) and displayed a slower degradation of photosynthetic pigments. Taken together, our studies suggest novel and crucial roles for TEM in adaptive growth as they modulate plant development in response to environmental changes such as increasing soil salinity.
A radiographic study of breed‐specific vertebral heart score and vertebral left atrial size in Chihuahuas
Authors: Puccinelli Caterina , Citi Simonetta , Vezzosi Tommaso , Garibaldi Silvia , Tognetti Rosalba 
Published: October 2020

AbstractAlthough echocardiography is the gold standard for the diagnosis of cardio‐structural disease, thoracic radiography is a rapid, cost‐effective, and widely accessible method for evaluating cardiac size in dogs. The vertebral heart score (VHS) and the vertebral left atrial size (VLAS) are established as objective measures of cardiomegaly on thoracic radiographs. However, several studies have shown significant variations in the VHS among different breeds. The Chihuahua is predisposed to both congenital and acquired cardiac diseases. The aim of this prospective, single‐center, cross sectional study was thus to evaluate the VHS and the VLAS in healthy adult Chihuahua dogs. A total of 30 Chihuahuas were included. The VHS values in our sample population of Chihuahuas were 10.0 ± 0.6 (95% range, 8.9‐11.0). This was significantly greater than the canine reference value of 9.7 ± 0.5 established by Buchanan and Bücheler (P = .002). The VLAS of Chihuahuas in our study was 1.8 ± 0.2 (95% range, 1.3‐2.1). This was significantly lower than the values previously reported by Malcolm et al (2.07 ± 0.25;P = .0004). The VHS and the VLAS were not influenced by sex, body weight, short or long hair, and body condition score in normal Chihuahuas. Our results indicated that breed‐specific reference values for radiographic VHS and VLAS are needed. In Chihuahuas, the values found in this study can be used as a normal reference in order to help avoid overinterpretation of cardiomegaly in these dogs.
Reviewer Acknowledgements
Authors: Young James 
Published: October 2020

International Journal of Social Science Studies (IJSSS) would like to acknowledge the following reviewers for their assistance with peer review of manuscripts for this issue. Many authors, regardless of whether IJSSS publishes their work, appreciate the helpful feedback provided by the reviewers. Their comments and suggestions were of great help to the authors in improving the quality of their papers. Each of the reviewers listed below returned at least one review for this issue.Reviewers for Volume 8, Number 6Aurora Pestaño, University of San Jose Recoletos (USJR), PhilippinesEncarnación ABAD ARENAS, National University of Distance Education (UNED), SpainHao Liu, Beijing Normal University, ChinaJehu Onyekwere Nnaji, University of Naples II, Italy and Globe Visions Network Italy, ItalyJibrin Ubale Yahaya, National Open University of Nigeria NOUN, NigeriaJulia M. Mack, Gannon University, USAMei-Ling Lin, National Open University, TaiwanQingzhi Huan, Peking University, ChinaRonaldo R. Larioque, NUEVA ECIJA UNIVERSITY OF SCIENCE AND TECHNOLOGY, PhilippinesShyue Chuan CHONG, New Era University College, MalaysiaUğur DEMİRCİ, Turkish National Police, TurkeyYusramizza Md Isa, Universiti Utara Malaysia, Malaysia James YoungEditorial AssistantOn behalf of,The Editorial Board of International Journal of Social Science StudiesRedfame Publishing9450 SW Gemini Dr. #99416Beaverton, OR 97008, USAURL: http://ijsss.redfame.com
Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure
Authors: Pace Raymond M. , Ritzel Jason 
Published: October 2020

Abstract
The Boiling Water Reactor (BWR) Mark I (Mk I) Containment Program was implemented by the Owner’s Group circa 1970 to mitigate the effects of small, intermediate and design bases, Loss of Coolant Accident (LOCA), pipe break accidents on the torus, supports, internal structures and attached piping [1 & 2]. One of the significant mitigation attributes implemented during the Mk I Program is Normal Operation (NO) with a drywell-to-wetwell Differential Pressure (dP) maintained by the plant Nitrogen Make-up System used to inert the Primary Containment (PC) [3]. The differential pressure served to reduce the downcomer water leg in the vent system resulting in significantly reduced vent system thrust and pool swell loads. The vent system is designed to transport the mixture of drywell atmosphere, steam, and water forced from the drywell by the increasing pressure post-accident, quenching it in the pool of water maintained in the suppression chamber (torus).
Based on plant experience, to sustain PC dP requires frequent venting of the Torus or nitrogen make-up to the drywell requiring Standby Gas System operation and cycling of PC vent and purge valves which places additional burden on the charcoal filters. The venting also places burden on Control Room Operators to perform the required actions and maintain Technical Specification (TS) limits.
Elimination of the dP benefits plant operation by minimizing cycling of PC Isolation Valves, reduction of burden on Control Room operators due to the wider pressure control envelop, reduction in Standby Gas System cycles extending charcoal filter life and a reduction of the nitrogen make-up [4]. Overall, the Utility estimates that elimination of the dP will provide an estimated cost savings of $0.5 M per year.
Relaxation of the Bolted Flange Connection
Authors: Taylor Robert 
Published: October 2020

Abstract
This study researches the total relaxation of a bolted flange connection, taking into account, the relaxation of various bolt grades in conjunction with different semi-metallic gaskets.
The test temperatures are: 300 °F (149 °C), 500 °F (260 °C), 650 °F (343 °C) and 800 °F (427 °C), where each temperature setting will cycle three times to obtain the relaxation value for each cycle.
The three types of bolt materials for evaluation include ASTM A193 B7, ASTM A193 B16 and ASTM B8M CL2 along with gaskets styles of spiral wound gasket with inner ring, spiral wound gasket with NO inner ring and the kammprofile gasket (grooved metal gasket with covering layers), all in accordance to ASME B16.20 – 2017.
The above variations and conditions will be tested at two different initial bolt stresses of 35,000 psi (241 MPa) and 65,000 psi (448 MPa) with a constant internal pressure of 150 psi (10.3 Bar).
The results will show relaxation values for the different bolt and gasket types versus the various temperature cycling conditions indicated above. Focusing on: does a certain gasket style offer lower relaxation properties through less creep and/or higher recovery? Does a certain bolt grade offer better stress retention? Is there variation in initial bolt stress for the different style of gasket? How does the initial bolt stress affect the relaxation properties of the bolted connection?
High Flux Reactor Continued Safe Operation: Time Limited Ageing Analyses
Authors: Stefanini L. , de Haan - de Wilde F. H. E. 
Published: October 2020

Abstract
The High Flux Reactor (HFR) is a multipurpose nuclear reactor located in Petten, the Netherlands.
With its 45 MWth it is one of the most powerful and versatile research reactors in the world. Its main roles are material irradiation and medical isotopes production. The output of the reactor in terms of medical isotopes is important at a global level (60% of European demand). Every day in the Netherlands alone 30.000 patients are treated using isotopes produced in the HFR. The importance of the HFR dates back in time. The HFR has been in service since 1961. Due to the long life (58 years to date) of the reactor an efficient integrated ageing management program (AMP) is envisaged as it is foreseen that the HFR will continue to operate for a prolonged period of time. The development of the AMP has begun in 2018 (CSO project) and will be completed in view of the IAEA CSO mission. The HFR is the second reactor in the world to undergo this type of IAEA review and one of the objectives of this project is to set a state of the art when it comes to research reactors long term operation.
The CSO project foresees four major sections: scoping and screening, development and improvement of plant programs, (re) validation of time limited ageing analyses (TLAAs) and realization of the ageing management program. In this paper the focus will lie on the TLAAs. The applicable TLAAs were scoped starting from the IGALLs TLAAs list. The TLAAs relevant for the HFR are: TLAA fatigue, TLAA reactor vessel, TLAA leak before break, TLAA manufacturing flaws TLAA beryllium and TLAA equipment qualification. The latter was developed in the framework of the equipment qualification plant program and does not figure as an independent TLAA in the CSO project. For each TLAA the principal problematics will be highlighted and the possible solutions illustrated.
Application of Nickel Electroplating for PWR Reactor Pressure Vessel Cladding Repair
Authors: Hwang Seong Sik , Kim Dong Jin 
Published: October 2020

Abstract
SA508 low-alloy steel for a reactor vessel was exposed to primary water in a pressurized water reactor (PWR) plant because the cladding layer of type 309 stainless steel for a reactor pressure vessel (RPV) was peeled off owing to an accident in which the thermal sleeve was detached. The advantage of electrochemical deposition (ECD) Ni plating techniques is that the RPV can be repaired without significant thermal effects, and Ni has sound corrosion resistance that can withstand exposure in primary water. The corrosion rate of the damaged part was assessed, and its trend was analyzed. The essential variables of Ni plating for repair of the damaged part were derived. These conditions are applicable variables for the repair plating device and have been carefully adjusted using the repair plating device. The process for establishing ASME technical standards called code case N-840 is described. The process for developing Ni-plating devices and the electrodeposition procedure specifications are described as well.
Advanced Component Fatigue Monitoring Approaches Using the Example of a Boiler Recirculation Pump
Authors: Rudolph J. , Bergholz S. , Metzger K. , Silber F. , Klenk A. , Müller T. 
Published: October 2020

Abstract
In the past, lifetime consideration of conventional power plant components focused on the creep behavior under internal pressure loading. Changing operating conditions towards flexible loads and load cycles as well as occurring damages underline the necessity to consider the fatigue and creep-fatigue behavior of the components. It is recommendable to integrate components such as boiler recirculation pumps into a fatigue monitoring program with continuous measurement of thermo-mechanical loads as a key feature. The paper describes the pilot fatigue monitoring of the boiler recirculation pump of block 8 of the GKM AG (including GKM, Framatome GmbH, KSB and MPA Stuttgart as actors). Thanks to the continuous data acquisition the thermal loading conditions were identified in much more detail than any available design data. The results of the measurement campaign were used for a qualified fatigue assessment based on the Fast Fatigue Evaluation (FFE) technology of Framatome. It was shown that the established monitoring approach (e.g. based on TRD301) is insufficient for complex geometries and loading conditions as it is the case for the boiler recirculation pump. The thermal loads as a consequence of temperature transients and temperature stratification are dominant. The consideration of these dominant loads in the fatigue assessment is indispensable. Based on a qualified fatigue evaluation approach reliable lifetime consumption, quantifications and extrapolations can be made for each component and fatigue relevant location. The FFE counts every closed cycle and allows for a continuous monitoring of the fatigue usage factor.
On Categorization of Seismic Load As Primary or Secondary for Multi-Modal Piping Systems
Authors: Labbé Pierre 
Published: October 2020

Abstract
Categorizing the seismic load requires calculating the input level associated with the ultimate capacity and comparing it to the level associated with the plastic yield. Therefore, an analysis of the seismically induced ductility demand in oscillators of variable frequencies was carried out by running non-linear time response analyses, the seismic input motion being simulated as samples of a stochastic process of central frequency fc. The response of oscillators with frequencies, f0, varying from 0.1 fc to 10 fc, was systematically analyzed. For every oscillator, 10000 time-responses were performed, corresponding to 1000 input samples multiplied by 10 input levels, covering a wide range of ductility demand up to 20.
Output is that seismic loads should be regarded as secondary for flexible oscillators (f0 &lt; fc) while it should be regarded as primary for very stiff oscillators (f0 &gt; cut-off frequency of the input motion, fcut), with intermediate situations for fc &lt; f0 &lt; fcut. A practical engineering rule is presented to incorporate this result when calculating the primary part of seismically induced streeses in a multimodal piping system. This rule is currently tested in the framework of the OECD-NEA international benchmark MECOS.
Mechanical Shock and Vibration Analysis of Spent Nuclear Fuel Carried by the Atlas Railcar
Authors: Klymyshyn Nicholas , Kadooka Kevin , Ivanusa Pavlo , Spitz Casey 
Published: October 2020

Abstract
Researchers at Pacific Northwest National Laboratory have completed a structural-dynamic analysis of spent nuclear fuel subjected to the mechanical shock and vibration environment that is anticipated during normal conditions of transport in casks carried by the Atlas railcar. The Atlas railcar is a new railcar design that is being developed specifically for the purpose of carrying spent nuclear fuel casks. The analysis used best-estimate railcar dynamics models of the Atlas railcar and considered 17 different spent nuclear fuel transportation cask systems, representing the current fleet of cask options. This work used NUCARS, a specialized railcar dynamics explicit finite element code to calculate railcar dynamic response to prescribed speeds and track configurations. The railcar dynamics models provided cask transient motion for a wide range of speeds and track conditions, generating a relatively large database of potential cask motion. All of the cask motion transients were then applied as loading conditions to LS-DYNA structural-dynamic models of a single fuel rod. The analyses predict that the Equipos Nucleares S.A./U.S. Department of Energy (ENSA/DOE) multimodal transportation test of 2017 provided a relatively stronger vibration environment than is expected from the Atlas railcar. This paper describes the analysis methods, the analysis results, and compares the results of the Atlas transportation analysis to the test results and analyses of the ENSA/DOE multimodal transportation test of 2017.
Experimental Studies of Typical Defects on Large Capacity Hoop-Wrapped Composite Cylinder of Steel Liner Based on X-Ray Digital Radiography Test
Authors: Chai Sen , Liu Sanjiang , Huang Liang , Jiang Yunxi , Bi Jianhao , Li Xiang 
Published: October 2020

Abstract
Tube trailers assembled with large capacity hoop-wrapped composite cylinder of steel liner (i.e., large capacity type 2 tube (LCT2T)) have shown an increasing trend in China. It is an urgent issue to detect nondestructively the defects of cuts, scratches and voids on the composite overwrap, and corrosion, cracks or other defects on the steel liner during their use and manufacturing processes. In this paper, the double-wall single-image technique of X-ray digital radiography (DR) method was studied for the typical defects on the LCT2T by making specimens of cracks and pitting corrosion on the steel liner, as well as cuts, scratches and void defects on the composite overwrap. The optimal penetration parameter was selected based on the identification of image quality indicators (IQI), and the detection sensitivity of the DR method for the typical defects on the LCT2T was obtained. The results showed that the above-mentioned artificial defects were effectively detected with double-wall single-image technique, and this technique had a higher detection sensitivity to longitudinal defects on the composite overwrap of the LCT2T than that to circumferential defects, as well as the detection sensitivity of steel liner defects was higher than that of composite overwrap defects.