bluuebunny/crossref_metadata_2025_split huggingface dataset:
Comparative 3D study of dental arches in children with microcephaly associated with congenital Zika syndrome, orofacial cleft, and without craniofacial anomalies
Authors: Moreira Machado Maria Aparecida Andrade , Passucci Ambrosio Eloá Cristina , Bringel Mayara , Moffa Eduardo Buozi , Siqueira Walter Luiz , Oliveira Thais Marchini 
Published: December 2022

AbstractIntroductionThe dentist participates in the treatment protocol for craniofacial anomalies in individuals from the first months of life.Objectiveto compare in a retrospective cohort study the morphometry of the edentulous palate of children microcephaly associated with congenital Zika syndrome (CZS), unilateral complete cleft lip and alveolus (UCL), and without craniofacial anomalies.MethodsForty‐five digitized dental molds composed the sample divided into three groups: CZS; UCL; and without craniofacial anomalies (control group). The following measurements were evaluated: intercanine and intertuberosity distances; dental arch length, area, volume, and mismatch superimposition. Parametric and non‐parametric tests were applied (α = 5%).ResultsCZS group showed the smallest means of intercanine distance and area than those of the other groups (p = .001 and p = .010, respectively). The dental arch length was greater in the CZS group than in the control group (p = .020). The evaluation of the mismatch superimposition showed that the CZS group had the lowest means of maximum distance and root mean square than that of the UCL group (p = .025 and p = .005, respectively).ConclusionCZS participants tended to palatal narrowing, while UCL individuals had parameters similar to those of the control group, despite the alveolus defect.
Customized Product Configuration Rule Intelligent Extraction and Dynamic Updating Method Based on the Least Recently Used Dynamic Decision Tree
Authors: Wang Zili , Ge Wenqi , Qiu Lemiao , Zhang Shuyou , Zhou Jiali , Hu Kerui , Fang Naiyu 
Published: December 2022

Abstract
In the traditional customized product (CP) configuration design system, the configuration rules in the database usually rely on the manual input and maintenance of experienced designers. In complex product design, configuration rules are numerous, complex, and difficult to understand. The way of human input based on experience consumes plenty of resources, which are strictly limited by experienced designers. This overreliance on those experienced designers has seriously restricted the development of enterprises. To address this problem, a least recently used dynamic decision tree (LRU-DDT) algorithm for CP configuration rule intelligent extraction and dynamic updating is put forward in this article. Based on the decision table majority (DTM) classifier, the condition attributes are first reduced. An improved J48 decision tree algorithm is proposed to extract the CP configuration rules. In addition, the CP configuration rules can be dynamically updated based on LRU-DDT. To verify the proposed method, the GB10 high-speed elevator configuration design process is taken as an example. The configuration rules are extracted and updated by the proposed algorithms. The results show that the configuration solution efficiency is improved by 16%.
Kinetostatic Analysis of Pneumatic Bending Soft Actuator Coupling With Revolute Joint
Authors: Wang Jiangbei , Wang Yuxuan , Fei Yanqiong , Chen Weidong 
Published: December 2022

Abstract
This paper presents the kinetostatic analysis of pneumatic bending soft actuator coupling with revolute joint, aimed to discover the bending performance of soft actuator wearing on physical joint of human body as exoskeleton. First, a new pneumatic bidirectional bending soft actuator is designed and its mechanical characteristic is obtained by experimental tests. Then, the kinetostatic analysis based on the principle of virtual work is conducted on the proposed soft actuator in the cases of bending alone and coupling with revolute joint. Finally, the kinetostatic equations are solved, and thus the bending performance of the soft actuator bending alone or coupling with revolute joint is obtained. This research mainly reveals the influence of coupling constraint on bending motions of soft actuator and lays a theoretical foundation for the pneumatic bending soft actuator to be applied in assist exoskeletons.
On the Probabilistic Endurance Prediction Approach for Turbomachinery Blades and Vanes
Authors: Kulkarni Davendu Y. 
Published: December 2022

Abstract
The design and aeromechanical assessments of turbomachinery blades and vanes comprise a wide range of complex processes that tend to be based on conventional deterministic methods. These processes often provide a “snapshot” evaluation of the new component designs at the nominal operating conditions. While the deterministic methods can predict the high cycle fatigue (HCF) endurance with reasonable accuracy, they assume that the conservative safety factors applied to cover for the parametric variations, uncertainties, and unknowns will not change during the product life cycle. This approach is intended to be conservative and in some cases may overlook the lack of robustness. The present paper proposes a robust design analysis approach based on probabilistic methodology for the aeromechanical assessment of rotor blades and stator vanes of turbomachinery. The robust design approach can account explicitly for the effects of design and manufacturing variability. This methodology can reduce the levels of conservatism in the deterministic approach and can provide a more thorough risk assessment. This paper offers a generalized aeromechanical analysis formulation based on probabilistic methods to evaluate the HCF capability of turbomachinery components. Herein, this methodology is demonstrated using a typical stator vane of an aero engine compressor and it is based on Monte-Carlo and design of experiment (DOE) simulations. The methodology consists of parametric sensitivity studies and identification of the most influential parameters that control the HCF endurance. Future ideas and roadmap of the aeromechanical probabilistic analysis capability development are also discussed.
Tribological Characteristics of Copper-Based Functionally Gradient Material for Wind Turbines Brake Pads
Authors: Rajesh Kannan K. , Vaira Vignesh R. , Govindaraju M. 
Published: December 2022

Abstract
Copper matrix incorporated with solid lubricant and hard ceramic reinforcement is a proven potential material for wind turbine brake pad applications. Though brake pads as bulk composites possess high wear resistance, hard ceramic reinforcements at the contact area weaken the joint strength with the brake caliper. This may lead to cataclysmic failure of the mechanical braking. This study aims to develop a functionally gradient materials (FGM) for brake pads that shows variations in composition and properties along its cross section. The brake pad comprises Cu, Fe, hBN, SiC, and Al2O3 powder to obtain a gradient composition profile. Metallographic studies showed the homogeneous distribution of minor matrix (Fe), solid lubricant (hBN), and reinforcement (SiC, Al2O3). Phase analysis was carried out using XRD, and Vickers microhardness tests were performed. A maximum hardness of 133.3 HV was obtained at the top layer of the FGM. Pin-on-disc wear apparatus was used to evaluate the wear-rate and the coefficient of friction (COF) of the sintered specimen at varied loads. Specimens exhibited a low wear-rate of 2.36 × 10−7 g/N m with 0.48 as the COF value at a maximum loading condition (70 N). Surface characterization (morphology, chemical composition, and phase composition) of worn specimens was performed using FESEM, EDS, and XRD analytical techniques. The results inferred that the predominant wear mechanism was oxidative and abrasive wear mechanism at high loads.
Validation of Gasoline Surrogates Through Thermodynamic Analysis of Spark-Ignition Engine
Authors: Patil Vishal , Singh Paramvir , Sonage Sachin , Kumbhakarna Neeraj , Kumar Sudarshan 
Published: December 2022

Abstract
The investigation aims to evaluate the impacts of commercial gasoline and gasoline surrogates on energy and exergy efficiencies in a spark-ignition (SI) engine. In this investigation, a new approach for formulating next-generation gasoline surrogates is investigated through testing these surrogates in a multi-cylinder SI engine. Energy and exergy analyses were carried out using the primary reference fuel-methylcyclohexane (PRF-MCH) blend (82.88% iso-octane + 9.16% n-heptane + 7.96% methylcyclohexane), primary reference fuel with 1,2,4-trimethylbenzene (PRF-1,2,4-TMB) blends (76% iso-octane + 9% n-heptane + 15% 1,2,4-trimethylbenzene and 61% iso-octane + 9% n-heptane + 30% 1,2,4-trimethylbenzene), and commercially available gasoline (gasoline) in an SI engine. The engine investigation results show that the PRF-MCH blend is a promising surrogate to reproduce the gasoline fuel engine characteristics such as combustion and emission characteristics of gasoline fuel. The detailed experiments were executed at the SI-engine speed conditions of 1500 rpm and 2500 rpm. It is found that PRF-MCH blend energy-exergy efficiencies are comparable to commercially available gasoline. It can also be concluded that engine testing in terms of energy-exergy analyses for proposed gasoline surrogates provides a qualitative and quantitative understanding of combustion behavior, emission characteristics, assessment of the effectiveness, and useful work potential gasoline surrogates.
Flow Characteristics Simulation of the Gas in the Containment Vessel of Molten Salt Reactor
Authors: Peng Honghua , Xia Xiaobin , Zhu Guifeng , Cai Jun , Zhou He 
Published: December 2022

Abstract
A containment vessel is usually designed to prevent the potential leakage of radioactive gas in molten salt reactor. Understanding the gas flow characteristics in the containment vessel is beneficial for mastering the radioactive level and the early monitoring and diagnosing when radioactive leakage accident occurs. In this paper, the simplified physical model of the containment vessel in a molten salt reactor was set up, and the gas flow characteristics driven by natural circulation in the containment vessel was studied by CFD code. The results shown that, when the gas enters into the upper chamber from the lower chamber due to buoyancy force, the gas velocity will reach a maximum value of 1.7 m/s where local jet occurs. The mass flow rate of gas between the upper and lower chambers is about 24.0 kg/h and the average circulation time in the containment vessel is about 7.3 hours. It is interesting to note that, the gas tends to flow upward in those annulus gaps with larger hydraulic diameter or near to the central region, indicating that when leakage is near to those regions, it will be easier and faster to flow into the upper chamber. The results provide the reference and guidance for radioactive gas monitoring.
Study on Reverse Heat Transfer Phenomenon of Steam Generator in Station Blackout Accident
Authors: Liu Yu-sheng , Zhuang Shao-xin , Xu Chao , Jing Jian-ping , Tan Si-chao 
Published: December 2022

Abstract
As the largest heat exchange equipment in the nuclear power plant system, steam generator (SG) is mainly responsible for the heat transfer matching between reactor coolant system (RCS) and secondary system in normal operation. The steam generator incorporating U type heat transfer tube also plays an important role under accident conditions due to the considerable feedwater inventory in its secondary side for design of most nuclear power plants, such as EPR, VVER, M310, etc.
However a direct passive cooling method is adopted in the Advanced Passive 1000 (AP1000), namely the emergency core cooling system is composed of passive residual heat removal (PRHR), core makeup tank (CMT), accumulator (ACC), and (In-containment Refueling Water Storage Tank (IRWST). As a result, the effect of heat exchange of SGs are usually ignored under accident conditions especially in the loss of coolant accidents (LOCAs) for the core decay heat is mainly transferred to the cold water in IRWST and atmosphere within containment via PRHR and other passive heat exchange systems.
However, the SGs may be relatively large heat sources in some transient conditions such as station blackout (SBO) occurring at Fukushima nuclear power plant in Japan. When the level of SG secondary side is fairly high while the decay heat power is low, a reverse heat transfer phenomenon which makes the SGs become an important heat source may occur as while as the PRHR operation.
In this paper, one SBO integral effect test carried out at ACME test facility is used to investigate the reverse heat transfer phenomenon in SG U-tube under non-LOCA transient. The temperature distribution in the U-tube, the flow rate of SG, the secondary pressure and feedwater level of SGs were studied. The results show that after the PRHR system is put into operation, the average temperature of RCS obtained by cold legs and hot legs decline rapidly. The water temperatures in the hot legs and hot chamber at SG inlet are far below that in the secondary side of SGs. The reverse heat transfer then occurs in the U-shaped tube bundle, and the heat transfer function of SGs are reversed namely the SGs become heat sources from heat sink in the accident process. Thus the cooling rate of RCS caused by PRHR is slowed down.
The equivalent power of reverse heat transfer in SGs were estimated based on the energy balance method and test data. The results show that the maximum power of SG reverse heat transfer reaches about than 20% of the decaying core power at the same time. The thermal hydraulic behavior of RCS, the temperature distribution in RCS are significantly affected and therefore make an effect on accident evolution process.
Comparison of Transitional Turbulence Models for Numerical Simulation of Flow Past a Sphere in a Pipe
Authors: Song Lei , Liu Xiongbin , Zhou Qin , Li Xiaotian 
Published: December 2022

Abstract
To develop a novel passive valve with a spherical disc for reactors, it is necessary to find a suitable numerical model to study the flow characteristics of flow past a sphere in confined spaces. The problem of flow past a sphere arises in many fields, and the phenomenon of drag crisis of a sphere in external flow, in which the drag coefficient of the sphere drops off suddenly as the Reynolds number increases, still occurs in internal flows. With the rapid development of transitional turbulence models in the past decade, we try to improve the drag coefficient prediction of flow past a sphere in a pipe with a wide range of Reynolds numbers using transitional turbulence models.
In this study, we numerically investigated the flow past a sphere in a pipe with a blockage ratio (the ratio of sphere diameter to pipe diameter) of 0.667 with three transitional turbulence models. The SST k-ω turbulence model without transition effects was also employed for comparison purposes. The studied Reynolds numbers ranged from subcritical region to supercritical region (5E+3 ⩽ Re ⩽ 3E+5). The skin friction coefficients and pressure coefficients of the sphere were calculated and compared for the four turbulence models. Compared to the measured drag coefficient data of a sphere in a pipe with a similar blockage ratio in the literature, the Intermittency transition model performs best in predicting the drag coefficient than the other turbulence models. None of the four turbulence models can adequately capture the drag crisis phenomenon, i.e., the calculated drag coefficients drop smoothly near the critical region of Reynolds numbers for all four turbulence models. The pipe wall effect is not neglectable in the estimation of the sphere drag coefficient by the pressure drop between the ends of the pipe.
Numerical Simulation of the Effect of Total Blockage of a Sub-Channel on Two-Phase Flow Through a 5 X 5 Rod Bundle
Authors: Ala Ayodeji A. , Tan Sichao 
Published: December 2022

Abstract
The study of the effect of blockage on two-phase flow parameters in rod bundle is of significance to the prediction of the thermal-hydraulic behavior of fuel assembly under hypothetical accident conditions. The two-phase flow computational fluid dynamics method was used to simulate the fluid flow phenomenon in 5 × 5 under no- and total sub-channel blockage conditions. The effect of the blockage on the void fraction is most significant in the sub-channel where it is located and the adjacent sub-channels. The effect of the blockage on other flow parameters extends as far as 46 Dh downstream of the blockage. There is an increase in the void fraction after the blockage as a result of bubble coalescence in the region. The effect of these different blockage conditions can provide a reference for the parameter setting of the sub-channel analysis codes.
Verification Dynamic Response for Sinusoidal Wave Flow in Narrow Rectangular Channel
Authors: Zhou Bao , Luo Liang , Yuan Hongsheng , Gao Puzhen 
Published: December 2022

Abstract
In this study, we experimentally studied the dynamic response of the sinusoidal single-phase flow in a horizontal narrow rectangular pipe. The experimental results show that, in narrow rectangular channel, the flowrate and the pressure drop also meet the first order dynamic response system phenomenon. The statistic results of prediction by dynamic response system theory shows that, for smaller frequency flow condition, the predictions are precisely, while for higher frequency, the prediction errors are relative bigger, which indicates a research point, high frequency sinusoidal flow, to put effort on.
One Dimensional Steady State Thermal Program for Liquid Metal Helical Coil Once-Through Tube Steam Generator
Authors: Yan Xiangyu , Zhu Lina , Shen Fengyang , Yang Dingbang 
Published: December 2022

Abstract
The Helical Coil tube type once-through Steam Generator (HCOTSG) is being used in an increasing number of reactor installations. Due to its special geometrical structure, the fluid heat transfer in the tube is enhanced by centrifugal forces, and has the advantages of compact structure, tolerable expansion and flexible arrangement. This paper takes the lead-bismuth helical coil tube type once-through steam generator as the study subjects. A self-developed steady-state calculation program is used to obtain the distribution of the thermal parameters on the primary and secondary sides and the length of the different heat transfer zones and the length of the helical tubes. In order to accurately analyse these characteristics of the lead-bismuth HCOTSG, the uniform flow model was selected in this paper, and the heat transfer zone on the secondary side was divided into single-phase liquid, two-phase and superheated steam zones, and the heat transfer relationship equation suitable for use in the HCOTSG was selected for the relevant calculations. A computational analysis of the Russian BREST and European ELSY steam generators was carried out using the numerical model to verify the accuracy of the program. The validated program was used to carry out the steady-state thermal analysis for the lead-bismuth HCOTSG. The results showed that the performance of the designed steam generator met the design requirements. This program provided more options for subsequent analysis of the steam generator under different operating conditions.
Experimental and Numerical Study on Convective Heat Transfer Characteristic in the Turbulent Region of Molten Salt in Shell-Side of Shell and Tube Heat Exchanger
Authors: Ding Meng-Ting , Chen Yu-Shuang , Fu Yuan 
Published: December 2022

Abstract
In order to better understand the heat transfer performance of shell and tube heat exchanger (STHE) with Fluoride salt as the heat transfer fluids, the steady-state heat transfer process of STHE with segmental baffles (STHE-SBs) in Fluoride-salt High Temperature Test Loop (FHTL) has been studied experimentally and numerically. Firstly, the Computational Fluid Dynamics (CFD) model was established to simulate the thermal performance of STHE-SBs. Then, thermal performance data such as temperature and heat transfer power were experimentally obtained under steady-state conditions of STHE-SBs at higher temperature (550–600°C), and to further verify the reliability of the simulation. The results show that the temperature distribution obtained by CFD is in good agreement with the experimental results, which indicates that the CFD program is reliable to describe the thermal performance of the STHE-SBs. On this basis, the effect of segmental baffles on the heat transfer enhancement of molten salt in shell side of STHE was discussed. The results show that the heat transfer enhancement effect of molten salt on the shell side of STHE-SBs is better than that of STHE without segmental baffles, and the increment of Nusselt number is about 64–73% during the low Reynolds number region. Finally, the heat transfer coefficient of molten salt in the shell side of STHE-SBs are fitted, which can be used in relatively wide ranges of Reynolds number and temperature.
Application of Self-Developed Advanced Three-Dimensional Simulation Software in Internal Flooding of Nuclear Power Plant
Authors: Wang Chenhui , Zhang Ran , Huang Xiaoyun , Wang Chao , Zhao Meng 
Published: December 2022

Abstract
Internal flooding in nuclear power plants is a possible internal disaster, which will lead to serious accidents in nuclear power plants, so it is necessary to evaluate for safety. CNIFA software is an advanced three-dimensional simulation software with independent intellectual property rights developed by China Nuclear Power Engineering Co., Ltd., which is specially used for internal flooding analysis of nuclear power plants. Compared with traditional flood analysis software, CNIFA has the advantages of good applicability and visualization. Interacted with E3D or PDMS software, the existing three-dimensional model of the nuclear power plant can be used directly as an input by CNIFA; the flooding scene inside the nuclear power plant can be dynamically simulated and the whole process of water flow spreading in the nuclear power plant in three dimensions can be clearly displayed by CNIFA. In this study, three -dimensional simulation software CNIFA is used to analyze the internal flooding safety of small reactor (ACP100), and some suggestions for design improvement are put forward. Firstly, the physical model of the plant (reduction ratio 1:10) is built to simulate the water flooding spread in the room of the nuclear power plant. The physical experimental results are compared with the simulation results of CNIFA. The results show that CNIFA has good applicability and accuracy in internal flooding safety assessment. Secondly, the safety assessment of the possible flooding event in ACP100 nuclear power plant is carried out through CNIFA, and the protective measures are taken for the important safety equipment in the plant according to the simulation results.