bluuebunny/crossref_metadata_2025_split huggingface dataset:
The spectrum of kidney dysfunction requiring chronic dialysis therapy: Implications for clinical practice and future clinical trials
Authors: Murea Mariana , Deira Javier , Kalantar‐Zadeh Kamyar , Casino Francesco G. , Basile Carlo 
Published: October 2021

AbstractStaging to capture kidney function and pathophysiologic processes according to severity is widely used in chronic kidney disease or acute kidney injury not requiring dialysis. Yet the diagnosis of “end‐stage kidney disease” (ESKD) considers patients as a single homogeneous group, with negligible kidney function, in need of kidney replacement therapy. Herein, we review the evidence behind the heterogeneous nature of ESKD and discuss potential benefits of recasting the terminology used to describe advanced kidney dysfunction from a monolithic entity to a disease with stages of ascending severity. We consider kidney assistance therapy in lieu of kidney replacement therapy to better reconcile all available types of therapy for advanced kidney failure including dietary intervention, kidney transplantation, and dialysis therapy at varied schedules. The lexicon “kidney dysfunction requiring dialysis” (KDRD) with stages of ascending severity based on levels of residual kidney function (RKF)—that is, renal urea clearance—and manifestations related to uremia, fluid status, and other abnormalities is discussed. Subtyping KDRD by levels of RKF could advance dialysis therapy as a form of kidney assistance therapy adjusted based on RKF and clinical symptoms. We focus on intermittent hemodialysis and underscore the need to personalize dialysis treatments and improve characterization of patients included in clinical trials.
Sulking behavior and the emergence of hurt feelings in young children
Authors: Hardecker David J. K. , Schmidt Marco F. H. , Haun Daniel B. M. 
Published: October 2021

AbstractWhen do hurt feelings develop? The emotion of feeling hurt is vital for close relationships because it signals that one has been devalued illegitimately, potentially eliciting guilt and the motivation to repair in the partner. We approached the question of when hurt feelings develop by studying the emergence of sulking behavior as an indicator of hurt feelings. In an online‐questionnaire study, parents and teachers hypothesized that children begin to sulk during the first 3 years (N = 125). In a cross‐sectional event‐based diary study, parents observed their 1‐ to 8‐year‐old children (N = 40). We found that the youngest child sulked at 20 months of age and that the probability of sulking was at 50% for a child at 25 months. Finally, we conducted a longitudinal event‐based diary study where parents observed their children from 16 months on until they sulked for the first time and, at the longest, until their third birthday (N = 29). We found that the probability of sulking was at 25% at 21 months, at 50% for a child at 24–25 months, and at 75% at 28 months, thus, confirming and specifying the results of studies 1 and 2. These findings indicate that the emotion of hurt feelings emerges mainly during the end of the second and the third year. We discuss the limitations of our approach and why and how the development of hurt feelings in the sense of an appraisal needs to be addressed differently.
Locating and categorizing causes of discomfort during transport of patients to medical facilities
Authors: Peulić Aleksandar , Peulić Miodrag , Jovanović Željko , Joković Miloš , Stojković Sanja , Vagić Nemanja 
Published: October 2021

AbstractThis article presents geographic information system usage in transportation management for comfort calculations, analysing vehicle vibration data measured during patient transportation. The main goal of this article is to develop a methodology for automatic discomfort cause recognition (DCR) that may be tested under real life conditions. We analysed differences between uncomfortable locations detected by passengers during patient transportation (according to their subjective opinions) and uncomfortable locations detected by the measurement system. The measuring system is based on the three‐axis accelerometer which is used to determine road comfort values for specific locations gathered by a GPS module. The results obtained were compared with data collected by passengers. During driving, when they experienced discomfort, passengers marked locations in near real time using the GIS. The data thus obtained were analysed with the data obtained by DCR. For the first time, the application of GIS provides analytical tools to create spatial data and define spatial data relations that determine comfort. Testing under real conditions, involving three separate cases, shows a high degree of correlation between the results. The proposed system allows dynamic comfort threshold criteria management and provides a visual representation of summarized tabular data.
Rethinking the geographies of finance for urban climate action
Authors: Robin Enora 
Published: October 2021

AbstractResearch on the geographies of finance for urban climate action has generated important insights into how climate agendas contribute to the financialisation of urban environments and strengthen the position of market actors in urban governance. However, by focusing on a limited set of financial instruments (e.g., green bonds, carbon credits), actors (e.g., real estate developers, private investors, international organisations), and projects (e.g., large‐scale infrastructure), existing studies overlook the heterogeneity of financial relations, initiatives, and actors that make possible urban climate action. This includes, for instance, the deployment of decentralised, small‐scale renewable energy technologies, or community‐led adaptation efforts. In this paper, I explore how theorisations of heterogeneous/hybrid infrastructure, diverse economies, and popular economies can advance current research, through the analysis of three decentralised renewable energy projects in France, the UK, and Zimbabwe. These concepts, I argue, can help us to expand our understanding of the multiple financial relations that underpin urban climate interventions and to explore their implications for the agency of different actors, particularly those who are most affected by climate change impacts.
Workers should take steps to mitigate surface lead exposure when using lead‐containing personal protective equipment
Authors: Mayer Monique N. , Sukut Sally L. , Blakley Barry , Waldner Cheryl L. , Adesina Kayode , Belotta Alexandra F. , Koehncke Niels K. 
Published: October 2021

AbstractVeterinary workers use lead shielding for protection against harm from ionizing radiation during diagnostic imaging. Surface lead on shielding has been reported as a potential exposure hazard. The purpose of this prospective, analytical, descriptive study was to measure surface lead on lead‐containing shielding in the field service and small animal radiology areas of a veterinary teaching hospital, and to examine potential risk factors for surface lead. Surface lead on a convenience sample of 54 lead shielding items was measured in a commercial laboratory using inductively coupled plasma mass spectrometry. The median and range of surface lead for aprons, thyroid collars, and gloves were 3.6 μg/dm2 (range, 1.3‐22.4 μg/dm2), 23.1 μg/dm2 (range, 2.6‐116 μg/dm2), and 134 μg/dm2 (range, 1.5‐155 μg/dm2), respectively. In the final multivariable analysis, the mean surface lead on thyroid collars and gloves was higher than on aprons (relative differences 4.8, 95% confidence interval [CI] 2.2, 10.5, P < 0.001; and 9.5, 95% CI 4.4, 20.6, P < 0.001, respectively). The mean surface lead on shielding in the worst condition was higher than on shielding in the intermediate and best conditions (P < 0.001). Lead shielding provides effective protection against the harmful effects of ionizing radiation, and shielding should always be worn during radiation exposure. Based on our findings and the common use of lead shielding in veterinary workplaces, we recommend that employers inform workers of this hazard and provide training on steps to mitigate exposure, including the use of disposable gloves when wearing lead shielding and handwashing after use.
Family involvement in transitional care from hospital to home and its impact on older patients, families, and health care providers: a mixed methods systematic review protocol
Authors: Thiengtham Supavadee , D’Avolio Deborah , Leethong-in Mayuree 
Published: October 2021

ABSTRACT

Objective:
The goal of this review is to synthesize the available evidence on family involvement in transitional care and its impact on patients’ and family caregivers’ health as well as health care providers’ satisfaction.

Introduction:
Involving families in transitional care from hospital to home has been undertaken to improve care quality, patient safety, and well-being. Successful family involvement in care depends on the interaction between the health care system and health care providers. However, family involvement in this process has not yet been systematically examined. This review will examine published quantitative and qualitative studies to create a better understanding of family involvement in transitional care.

Inclusion criteria:
This review will consider family involvement in transitional care, encompassing older patients, family caregivers, and health care providers. The quantitative component will compare family involvement interventions with standard care or alternative interventions. Outcomes will be grouped by older patients, family caregivers, and health care providers. For the qualitative component, the subjective experiences of all groups will be explored.

Methods:
Eligible quantitative, qualitative, and mixed method studies will be searched in databases and gray literature sources. The review will consider studies from 1989 to the present, published in English or Thai. Study selection, critical appraisal, data extraction, and data synthesis will be undertaken by two independent reviewers following the segregated JBI approach to mixed methods reviews.

Systematic review registration number:
PROSPERO CRD42020191464
Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section
Authors: Liu Qingqing , Diaz Julio , Petrov Victor , Burak Adam , Manera Annalisa , Kelly Joseph , Sun Xiaodong 
Published: October 2021

Abstract
Void fraction is one of the most important parameters that affect two-phase flow heat transfer and pressure drop. In this paper, a commercial gamma densitometer and a high-speed X-ray radiography system developed at the University of Michigan (UM) are used to measure the void fraction in two-phase boiling flows, with water as the working fluid, in a tubular test section. The test section is made of Incoloy 800H/HT with a total length of 1.589 m, an inner diameter of 12.95 mm, and a wall thickness of 3.05 mm. These two instrumentation systems are installed on a traversing platform that travels along the vertical test section for measurements at multiple elevations. Subcooled flow boiling and natural convection boiling experiments are performed to measure the void fraction in the test section. Flow visualization images are obtained for bubbly and slug flows from the X-ray radiography system. The wall temperature of the test section is measured at 17 elevations by thermocouples. In addition to the experiments, a multiphase computational fluid dynamics (MCFD) model is developed using ANSYS FLUENT to simulate the subcooled flow boiling. The measured wall temperature and void fraction from the experiments are compared with the MCFD simulation results. The RMS (Root mean square) errors are 3.6% and 16.1% for the wall temperature and void fraction, respectively, between the experimental data and MCFD simulations.
Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors
Authors: Sasaki K. , Miura S. , Fukumoto K. , Goto M. , Ohashi H. 
Published: October 2021

Abstract
Cs-Bi and Cs-Sb absorbed graphite samples (Cs-Bi/graphite and Cs-Sb/graphite) were synthesized and their high temperature chemical stabilities were tested up to 1500 °C by TG and analyzed by TEM-EDS for the development of Cs trap material in high temperature gas-cooled reactor (HTGR) fuel particles. It was observed that Cs was stabilized by Sb but not by Bi in the specimens after the TG test. A rapid weight loss from 800 to 1000 °C may be caused by evaporation of Cs (boiling point: 671 °C) was seen in the TG result of both specimens. Precipitated Cs-Sb substance in the graphite matrix were not resolved even after the 1500 °C heating. The chemical composition of the Cs-Sb was specified as Cs3Sb. The experimental results suggest that Sb have potential to be a Cs getter material in graphite matrix. Long term heating test should be performed to confirm adaptability of Sb for Cs trap material in HTGR fuel particles.
Oxidation Behaviors of the High Temperature Alloys in the Impure Helium and Argon
Authors: Zheng Wei , Li Haoxiang , Wang Qiuhao , Yin Huaqiang , He Xuedong , Fan Hua , Ma Tao 
Published: October 2021

Abstract
The trace number of impurities such as CO, H2, H2O, and CH4, which existed in the primary coolant of High Temperature Gas-Cooled Reactor (HTGR), has an adverse effect on the structural metallic materials at elevated temperatures. Mainly, it includes oxidation, decarburization, and carburization. The simulative corrosion test was conducted on the four alternative materials of the steam generator in HTGR: Inconel 617, Incoloy 800H, Hastelloy X, and T-22. At 950°C, the alloys were exposed to the helium and argon with impurities for 50 hours. The corroded samples were analyzed by weighing, scanning electron microscope (SEM), and electron probe microanalyzer (EPMA). Inconel 617, Incoloy 800H, and Hastelloy X formed the chromerich scale on the surface. Due to the low oxidizable elements content and low oxygen partial pressure, the continuous scale of T-22 alloy was not observed. Although Inconel 617 and Incoloy 800H formed the thick oxidation layer, pores on the surface may weaken the corrosion resistance. For Inconel 617, the Chromium Depletion occurred near the corrosion layer. In addition, the high temperature alloys showed similar corrosion behaviors in the helium and argon with trace impurities. This proves that the corrosion behavior of superalloys at 950°C will not change after replacing helium with argon, providing an alternative to helium in the corrosion test atmosphere.
Experimental Observation of Nucleate Boiling Entrainment in a Liquid Film
Authors: Tabuchi Junpei , Narushima Yuki , Katono Kenichi , Okawa Tomio 
Published: October 2021

Abstract
Many studies have been conducted on droplet entrainment in an annular flow regime, but little is known about droplet entrainment caused by nucleate boiling. In this report, visualization results of droplet entrainment caused by nucleate boiling are described. We observed two processes of droplet entrainment. The first one causes bubble bursting at a water surface. The second one causes filament breakup which occurs when the vapor bubble reaches and collapses at the interface between air and liquid. From comparison of the phenomena for the two processes, we found that the diameters of the droplets and vapor bubbles were considerably different. Using the results of this research allows the effect of forced convection to be taken into account. In the future, we plan to expand the amount of data and develop a boiling entrainment model under forced convection conditions.
Analysis of Friction Factor of Two-Phase Flow in Helically Coiled Tubes
Authors: Jiang Baihui , Zhou Zhiwei , Ji Yu 
Published: October 2021

Abstract
With compact structure and enhanced heat transfer capacity, helical-coiled once through steam generators (HTSGs) are widely used in the small modular reactors (SMRs). Nevertheless, the inside centrifugal forces make the flow more complicated, and increase the frictional pressure drop, which is closely related to the dual test of alternating thermal stress and flow instability. Therefore, the analysis of the friction factor in helically coiled tubes is significant to the efficient and safe operation of HTSGs.
While the friction factor of single-phase flow in helically coiled tubes was fully studied and extensive correlations have been validated by a large amount of experimental data, the friction factor of two-phase flow still lacks feasible prediction due to its much more complexity. The existed correlations of two-phase flow in helically coiled tubes are mostly based on specified experimental parameters, so the applicable range is limited. Few scholars have tried to extend these correlations to broader applicability, but the trivial applicable range is unsuitable for program development or engineering design, which needs an accurate prediction of friction factor in a wider range.
In this paper, existing frictional pressure drop correlations are investigated. The accuracy of single-phase frictional pressure drop correlations is verified through the comparison of calculation results. Since the known experimental data cannot cover a wide range of parameters, two assumptions are proposed, and the rationality is verified through the existing experimental data and calculation analysis. Based on the two assumptions and calculation, a set of calculation correlations for frictional pressure drop of two-phase flow in helically coiled tubes are proposed. The accuracy of this calculation model is validated by experimental data. The scope of application of this model is: D / d = 15–100, P = 0.12–6.3MPa, G = 200–1500kg / m2s, which is sufficient to support the design and operation of steam generators and the development of the simulation programs.
Sensitivity Analysis on the Blast Resistance of Steel Concrete Structure Wall Based on CONWEP
Authors: Ren Guopeng , Pan Rong , Sun Feng , Li Liang 
Published: October 2021

Abstract
In the modern society, more and more explosive accidents and explosive terror attacks have happened around the world. These explosions not only inflict heavy casualties and property loss, but also cause serious damage to related structures. The outer wall of the nuclear island plant of newly constructed nuclear power unit is usually designed as the steel concrete (SC) structure to prevent from explosion and aircraft impact. This paper selects the steel concrete structure wall composed of surface steel plate, stud, tie bar and concrete as the study object. It adopts classical explicit nonlinear dynamic analysis software ANSYS/LS-DYNA to conduct a series of parameter sensitivity analysis on the impact of blast resistance of the steel concrete structure wall based on the CONWEP method. These parameters include: the explosive scaled distance, thickness of the steel plate, thickness and grade of the concrete, diameter and spacing of tie bars, etc. The analysis results indicate that the above mentioned parameters, especially the explosion scaled distance, the thickness of the wall and the spacing of tie bars, affect the blast resistance capacity of the wall. This paper contributes to the guiding and referencing significance for the design and optimization of the steel concrete structure outer wall of nuclear island plant.
All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor
Authors: Ma Qian , Yu Zhitong , Sun Peiwei , Jia Yuwen , Wu Shifa 
Published: October 2021

Abstract
Topaz-II is a space nuclear reactor developed by the Former Soviet Union. It is a thermal-neutron reactor with UO2 ceramics as fuel. Electricity is generated based on the principle of thermoelectric conversion. The reactivity is controlled by several groups control drums. Its lifetime can be three years and its reactivity feedback and further dynamic characteristics are varying with its lifetime. The positive reactivity feedback characteristics and different dynamic characteristics in different lifetime make it changeling to design a suitable control system for Topaz-II.
All-coefficient adaptive control is a single-input single-output adaptive control method applied to a parameter unknown, linear time invariant or slowly varying object. In some specific conditions, it is also suitable for the non-linear systems. In this method, the model where the sum of coefficients is equal to one is reconstructed based on the original dynamic model. All coefficients in this model can be identified. Therefore, it is possible to realize the optimal control.
Firstly, the model of Topaz-II nuclear reactor system is built. It includes point-reactor kinetics model with six groups delayed neutrons, a one-dimensional lumped transient thermal model of the nuclear fuel element and the moderator, a thermionic model of the converters, a control drum drive model. The reactivity feedbacks with fuel temperature and moderator are considered. Based on the model, the dynamic characteristics are analyzed.
Then, with the nonlinear model of Topaz-II nuclear reactor system, the transfer functions are obtained and analyzed. Based on the transfer functions, the model where the sum of coefficients is equal to one is built by using the all-coefficient adaptive control method. After dealing with the parameter and analyzing the error, the all-coefficient adaptive control systems are designed.
To evaluate the performance of the control systems, power maneuvering events including a 30%FP (Full Power) step change and a reactivity disturbance of 0.0065 are simulated. The responses with traditional and proposed control methods are evaluated and compared. The simulation results show that the all-coefficient adaptive control system has a better performance in settling time and overshoot compared with those with traditional PID controller.
Fragmentation and Cooling Behavior of a Simulated Molten Core Material Discharged Into a Sodium Pool With Limited Depth and Volume
Authors: Matsuba Ken-ichi , Kato Shinya , Kamiyama Kenji , Akayev Assan S. , Baklanov Viktor V. 
Published: October 2021

Abstract
In order to obtain experimental knowledge on fragmentation and cooling behavior of molten core material discharged into regions where the depth and volume of sodium are limited, a series of out-of-pile experiments using alumina (Al2O3) as a simulated molten core material was conducted at an experimental facility of National Nuclear Center of the Republic of Kazakhstan (NNC/RK). In this experimental series, approximately 9 kg of molten alumina was discharged through a duct of 40 mm in inner diameter into a test vessel (200 mm in depth and 300 mm in inner diameter) installed in an outer large vessel filled with sodium. The discharge mass of molten alumina and the dimension of the inner test vessel were determined so that the bulk temperature of sodium inside the test vessel could exceed its saturation temperature. Flow holes were provided in the top lid of the inner test vessel to allow sodium flow between the inner and outer vessels. The shape of solidified alumina recovered from the inner test vessel after this experiment was not ingot-like but fragmented debris. As a possible mechanism for such a debris shape, Fuel-Coolant Interaction (FCI) at the molten alumina jet impingement on the bottom of the test vessel might have promoted jet fragmentation, and heat exchange by sodium inflow and outflow through the flow holes might have contributed to effective cooling of molten alumina.