bluuebunny/crossref_metadata_2025_split huggingface dataset:
Sequencing artifacts in the type A influenza databases and attempts to correct them
Authors: Suarez David L. , Chester Nikki , Hatfield Jason 
Published: February 2014

BackgroundThere are over 276 000 influenza gene sequences in public databases, with the quality of the sequences determined by the contributor.ObjectiveAs part of a high school class project, influenza sequences with possible errors were identified in the public databases based on the size of the gene being longer than expected, with the hypothesis that these sequences would have an error. Students contacted sequence submitters alerting them of the possible sequence issue(s) and requested they the suspect sequence(s) be correct as appropriate.MethodsType A influenza viruses were screened, and gene segments longer than the accepted size were identified for further analysis. Attention was placed on sequences with additional nucleotides upstream or downstream of the highly conserved non‐coding ends of the viral segments.Results and ConclusionsA total of 1081 sequences were identified that met this criterion. Three types of errors were commonly observed: non‐influenza primer sequence wasn't removed from the sequence; PCR product was cloned and plasmid sequence was included in the sequence; and Taq polymerase added an adenine at the end of the PCR product. Internal insertions of nucleotide sequence were also commonly observed, but in many cases it was unclear if the sequence was correct or actually contained an error. A total of 215 sequences, or 22.8% of the suspect sequences, were corrected in the public databases in the first year of the student project. Unfortunately 138 additional sequences with possible errors were added to the databases in the second year. Additional awareness of the need for data integrity of sequences submitted to public databases is needed to fully reap the benefits of these large data sets.
Developing and testing a discharge planning decision support tool for hospitalized pediatric patients
Authors: Holland Diane E. , Conlon Patricia M. , Rohlik Gina M. , Gillard Kris L. , Tomlinson Angie L. , Raadt Dawn M. , Finseth Onalee R. , Rhudy Lori M. 
Published: February 2014

AbstractPurposeTo develop and test a decision support tool that identifies patients who would benefit from early consult with discharge planners.Design and MethodsA predictive, correlational design was used with parents/guardians of children (1 month to 18 years; N = 197). Data were collected by interviews and record reviews. Expert consensus determined referral to discharge planning.ResultsMean age was 8.7 years; mean length of stay was 7.5 days. Forty percent (n = 79) were identified for early referral. The variable “substantial post‐acute care needs” had the strongest association with expert consensus (internally validated AUC = 0.79).Practice ImplicationsFindings from this study provide preliminary evidence for a decision support tool to improve the discharge planning process by reducing individual decision‐making variability through systematic matching of patient needs to service delivery.
Normal values for solid‐state esophageal high‐resolution manometry in a European population; an overview of all current metrics
Authors: Weijenborg P. W. , Kessing B. F. , Smout A. J. P. M. , Bredenoord A. J. 
Published: February 2014

AbstractBackgroundEsophageal high‐resolution manometry (HRM) allows accurate evaluation of esophageal motility. Normal values for HRM were established in the United States and several new parameters were introduced since. We aimed to provide a complete set of normal values for HRM obtained in a European population, including all current metrics used to describe the function of the upper esophageal sphincter (UES), the esophageal body, and the esophagogastric junction (EGJ).MethodsFifty healthy volunteers underwent esophageal HRM. Subjects swallowed 10 liquid boluses in supine position, after which UES, EGJ, and contraction wave parameters were evaluated. Mean and median values with 5–95th percentile ranges were calculated.Key ResultsThe normative thresholds (5–95th percentile) for the various parameters were; UES resting pressure 34.6–137.7 mmHg, UES residual pressure 0.0–8.5 mmHg, UES 0.2‐s integrated relaxation pressure (IRP) 0.0–14.5 mmHg, EGJ length 3.1–6.3 cm, EGJ resting pressure 3.0–31.2 mmHg, EGJ 4‐s IRP 2.0–15.5 mmHg, intrabolus pressure (IBP) 6.6–19.5 mmHg, distal contractile integral 178–2828 mmHg*s*cm, contractile front velocity (CFV) 2.9–5.9 cm s−1, distal latency 5.4–8.5 s, and transition zone length 0.0–8.2 cm.Conclusions & InferencesMost HRM parameters assessed in this study resemble the previously described values on which the current criteria are based, supporting the widespread use of these criteria for clinical purposes. However, vigor of the esophageal contraction was lower and transition zone length larger than in previous reports. Peristaltic breaks occur frequently in healthy subjects.
Dose requirements of remifentanil for intubation in nonparalyzed Chinese children
Authors: Liu Hua‐Cheng , Tao Wei‐Ke , Zeng Rui‐Feng , ShangGuang Wang‐Ning , Li Jun , Huang Wen‐Guang , Dong Zhang‐Lei , Wang Xin , Lian Qing‐Quan 
Published: February 2014

SummaryBackgroundThe objective of this study was to determine ED50 and ED95 of remifentanil for intubation combined with propofol in nonparalyzed Chinese children.MethodsForty‐seven American Society of Anesthesiologists Class I children aged 4–11 years weighing 14–33.5 kg underwent general anesthesia with 2.5 mg·kg−1 of intravenous propofol followed by remifentanil in Wenzhou, China. The initial dose of remifentanil was 2.5 μg·kg−1 injected over 60 s. Intubation was attempted 30 s after the completion of remifentanil injection. Level of difficulty to intubate was graded on a scoring system. If the initial intubation condition was deemed satisfactory, subsequent remifentanil doses were decreased by 0.25 μg·kg−1. If the intubating condition was deemed unsatisfactory, subsequent remifentanil doses were increased by 0.25 μg·kg−1. Mean arterial pressure, heart rate, and pulse oximetry were documented before and after induction, immediately after intubation, and 1 min after intubation.ResultsThe ED50 of remifentanil used to render a satisfactory intubating condition used in combination with 2.5 mg·kg−1 of propofol in nonparalyzed Chinese children was 2.30 μg·kg−1 (95% confidence interval: 2.28–2.31 μg·kg−1), and the ED95 is 2.75 μg·kg−1 (95% confidence interval: 2.59–3.35 μg·kg−1). These doses were lower than previously reported.ConclusionWhen used in combination with 2.5 mg·kg−1 of intravenous propofol, ED50 and ED95 of remifentanil for adequate intubation in nonparalyzed children were lower than previously reported, at 2.30 and 2.75 μg·kg−1, respectively.
Do educational outcomes correspond with the requirements of nursing practice: educators' and managers' assessments of novice nurses' professional competence
Authors: Numminen Olivia , Laine Tuija , Isoaho Hannu , Hupli Maija , Leino‐Kilpi Helena , Meretoja Riitta 
Published: February 2014

ObjectiveThis study evaluated weather educational outcomes of nurse education meet the requirements of nursing practice by exploring the correspondence between nurse educators' and nurse managers' assessments of novice nurses' professional competence. The purpose was to find competence areas contributing to the acknowledged practice–theory gap.DesignA cross‐sectional, comparative design using the Nurse Competence Scale was applied.SubjectsThe sample comprised nurse educators (n = 86) and nurse managers (n = 141).MethodsDescriptive and inferential statistics were used in the data analysis.Main outcome measuresEducators assessed novice nurses' competence to a significantly higher level than managers in all competence areas (p < 0.001). The biggest correspondence between educators' and mangers' assessments were in competencies related to immediate patient care, commitment to ethical values, maintaining professional skills and nurses' care of the self. The biggest differences were in competencies related to developmental and evaluation tasks, coaching activities, use of evidence‐based knowledge and in activities which required mastering a comprehensive view of care situations. However, differences between educators' and managers' assessments were strongly associated with their age and work experience. Active and improved collaboration should be focused on areas in which the differences between educators' and managers' assessments greatly differ in ensuring novice nurses′ fitness for practice.
On the absence of solar evolution‐driven warming through the Phanerozoic
Authors: Waltham David 
Published: February 2014

AbstractReconstructed temperatures through the Phanerozoic indicate a gradual cooling or, at best, no significant temperature trend, despite a 4.4% increase in solar heating. It is possible that an underlying warming trend has simply been swamped by ‘noise’ due to significant data‐errors and/or natural fluctuations. Alternatively, the lack of warming may indicate cooling by biological and/or geological processes, which happen to have the right amplitude to cancel the effects of solar warming. This paper demonstrates that the absence of Phanerozoic warming cannot be explained as a warming trend hidden by noise. It also shows that, given widely accepted estimates of climate sensitivity, it cannot be explained as cancellation by negative feedback in the climate system. The Gaia hypothesis, anthropic selection or some other unconventional mechanism may therefore have to be invoked to explain the absence of long‐term warming through the Phanerozoic.
Flow Characteristics of Fuel Bundle With New Mixing Vane Design
Authors: Yu Wenchi , Pang Zhengzheng , Zhou Yuemin , Li Weicai , Chen Xiaoming 
Published: February 2014

The prevalent fuel assembly geometry of Pressurized Water Reactors (PWR) is constituted of open-lattice rod bundles arranged in a square configuration with grid spacers. In order to enhance the coolant mixing effects across the adjacent flow channels, mixing vanes are added to the grid. The presence of the spacer grids with mixing vanes imposes two opposite effects that would affect the thermal-hydraulic characteristics in the core. Grid spacers with optimized mixing vanes will generate more effective swirl flow across the neighboring subchannel to enhance the local heat transfer rate from the fuel rod cladding to the core coolant downstream the grids, however, it would slightly increase the local pressure drop that would render an negative effect, though it is small, on the core thermal margins.
The key elements for mixing effects, such as mixing length, cross and swirl flows, hinged on the coolant flow that is redistributed by the mixing vanes. This paper presents a mixing vane grid design (or concept) that could increase the effectiveness of heat transfer. Its structure includes flow-oriented section and vane. Flow oriented channel section is set on the other side of the neighboring cell which is different from a conventional mixing vane design. For mixing effect, there exists a balance between the incoming flow area and the bending angle. It also effectively draws more coolant from the adjacent cells to the mixing vane. Thus, it is an effective way to create a stable swirl flow downstream. The flow mixing impact travels much longer than that caused by the most conventional mixing vanes.
Burnup Credit in the Criticality Safety Analysis of Spent Fuel in Transportation and Storage Systems
Authors: Soloviov Vladyslav 
Published: February 2014

In this paper accounting of spent nuclear fuel (SNF) burnup of RBMK-1000 only with actinides has been performed.
The following characteristics were analyzed: initial fuel enrichment, burnup fraction, axial burnup profile in the fuel assembly (FA) and fuel weight.
As the results show, in the first 400 hours after stopping the reactor, there is an increase in the effective neutron multiplication factor (keff) due to beta decay of 239Np into 239Pu. Further, from 5 to 50 years, there is a decrease in keff due to beta decay of 241Pu into 241Am. Beyond 50 years there is a slight change in the criticality of the system.
Accounting for nuclear fuel burnup in the justification of nuclear safety of SNF systems will provide an opportunity to increase the volume of loaded fuel and thus significantly reduce technology costs of handling of SNF.
Dynamic Balance and Vibration Control on Field of the Fan L9DVN272ZV in Lingao Nuclear Power Plant
Authors: Dong Xiangxiang , Li Zhaojie 
Published: February 2014

Dynamic balancing is an effective measure for adjusting an unbalanced fan rotor mass to within its allowable limits. This is a typically implemented method used in nuclear power plants for resolving fan rotor unbalance conditions.
The operating spectrum of L9DVN272ZV has always been the fundamental component of the vibration frequency since finding the fan high vibration. This paper discusses the balance process of the subject fan. The vibration data collected was evaluated to aid in selecting the proper method of vibration attenuation. Ultimately the fan vibration was reduced to within the specified allowable limits.
A Method for RCCA Drop Analysis
Authors: Liu Tong , Huang Heng , Li Peng , Xu Wei , Zhou Yuemin , Yang Yiren 
Published: February 2014

The control rod drop time is one of the most important parameters for safety analysis. The calculation accuracy of control rod drop time will be affected if ignoring the transverse vibration, which is mainly caused by the fluid-structure interaction between the RCCA (rod cluster control assembly)s, guide tubes and the fluid interaction.
A new method for RCCA drop analysis is presented in this paper. The transverse equations of motion are established considering fluid-elastic structure interaction, assuming the fluid is incompressible laminar flow. And the vertical equations of motion are established considering the gravity force of RCCAs, the fluid resistance, and the friction force led by collision.
A computer program based on this method is used to calculate the control rod drop time, the impact and the dynamic response of RCCA. The analysis results are compared with those of the in-house code, which is used for commercial design. It shows the computer program using the new models provides a useful tool in the design of RCCAs and fuel assemblies.
Experimental Investigations of Control Rod Drive Mechanism
Authors: Lu Guangyao , Lu Zhaohui , Xiang Wenyuan , Lv Yonghong , Huang Wenyou , Zhou Jianming 
Published: February 2014

The control rod drive mechanism (CRDM) is installed on the CRDM socket in reactor pressure vessel (RPV). Directed by Rod Control and Rod Position Indicating System (RGL), CRDM can impel the control rods move up and down in the nuclear reactor core, which implements the functions of reactor start-up, power regulation, power maintaining, normal reactor shutdown and abnormal (accident) shutdown.
CRDM was developed by China Nuclear Power Research Institute (CNPRI). Several design improvements were conducted to solve the problems appeared in the operation of nuclear power station. Test bench was also set up and cold tests were carried out to investigate the characteristics of CRDM. The cold tests included lifting experiment, inserting experiment, rod drop experiment. And studies were carried out to analyze the signals of lifting coil, moving coil, stationary coil and the vibration signals. The test results show that the design of CRDM is reasonable and the operation is reliable.
The Influences of Significant Nuclear Events on Public Attitude and Acceptance
Authors: Liu Mingye 
Published: February 2014

In this paper, the influence of significant nuclear events on public attitude, and the reaction, i.e., public attitude on the development of nuclear industry have been studied. Though it has been widely known that nuclear is a type of clean, green and effective source of energy, due to the characteristics of nuclear, for most common people, they seldom pay attention to the nuclear power plants (NPPs) or the entire nuclear industry except NPPs are built near the residence of their own, or when some catastrophic failures occur. This fact leads to that when the public’s attention is attracted to nuclear, the effects on their attitude to nuclear are often negative. Even if there is positive news about nuclear, in most cases, the public will still be worried and prudent. That is one of the reasons why though the nuclear power related techniques has been developing rapidly, in some countries the usage of nuclear power is still quite limited.
In order to carry the development of nuclear power forward, to improve the public acceptance is as important as to improve nuclear related science and technology. This paper focuses on how the significant events related to nuclear influence the public acceptance, which will have direct or indirect effects on the development and/or policy of nuclear industry in a country, even the whole world. Additionally, this paper discusses possible and proper solutions to improve the public acceptance to NPPs and nuclear related techniques.
Very Slow Pebble Flow: A New Research Field
Authors: Jiang Shengyao , Yang Xingtuan , Gui Nan , Tu Jiyuan 
Published: February 2014

As well known, the very slow pebble flow (VSPF) exists in the pebble bed high temperature gas cooled reactor, which is regarded as the 4th generation of nuclear power plant, one of the most promising reactors in the 21th century. Unfortunately, we still know very little on the fundamentals of the VSPF, a specific type of granular flows.
In general, a granular flow is a collection of a large number of discrete but closely packed solid particles. A granular flow may behave as either an elastic solid or a fluid, depending on the local stress conditions. A rapid granular flow behaves much more like a fluid rather than a solid collection, and sometimes can even be analogically analyzed by the kinetic theory. However, the very slow granular flow (VSGF) is showing its elastic solid behavior at any instantaneous time and fluid-like behavior in a long time. It can shear like fluid, dissipate energy by collision, and also it can support loads and form finite piling slopes like solid. It is more complicated than the rapid flow and cannot be easily analyzed solely by the fluid or kinetic theories.
We regard the VSPF as a special VSGF. In the pebble bed under gravity, the pebbles flow out of the bed very slowly, almost one-by-one. Thus, the flow-out process is an intermittent or discrete process in time. We can regard each flow-out process as an “original disturbance” (OD), and the transfer process of OD throughout the bed as a “subsequent disturbance” (SD). The SD is decaying in time as the pebble collision is dissipative. Thus, the VSPF can be specifically defined as a special case in which the OD and SD processes are not overlapped. In other words, the effect of SD has already been dissipated almost completely before the next OD occurs.
In this study, we just show some examples for the interesting phenomenon of VSPF both experimentally and numerically. Based on the OD and SD theory, we show the typical processes and basic characteristics of OD and SD to validate their existences and justify the definitions of VSPF by the OD and SD.
Several Constraint Methods for Avoiding Thermal Stress Distortion on Structure Simulating Calculation
Authors: Dai Shoutong , Yin Hao 
Published: February 2014

When the conventional thermal stress analysis is made using simulation software, the thermal expansion is regarded to be completely limited on the fixed place. The zero displacement constraint is so applied. But in fact the structure can still expand in some degree, the boundary conditions of the simulation model are so strict seriously that the calculated stress will be far greater than the actual values, which is called “thermal stress distortion” in this paper.
In order to reduce the conservative degree some of the structure constraints should be set free according to the actual structure to make the structure extend appropriately. At the same time the integrity of the applied constraint should be noticed specially. The rigid motion shouldn’t be expected to exist because of the inadequate constraints.
The paper presents several constraint methods for avoiding the thermal stress distortion according to the typical structure of nuclear engineering: “extension constraint”, “column coordinates constraint” and “segmentation and alternate constraint”.
The “extension constraint” method is suitable for the structure simulation which distortion locates near the constraint place. But it can only eliminates parts of the distortion. The “column coordinates constraint” and “segmentation and alternate constraint” methods both can eliminate all of the distortion. The former is only applicable for the rotational structure, while the latter is suitable for frame and rotation structure, what is important is that the latter also provides an idea for structure design to eliminate the thermal stress distortion: setting expansion gap.
Role of Irradiation Embrittlement in RPV Lifetime Assessment
Authors: Brumovský Milan , Kytka Miloš 
Published: February 2014

Integrity and lifetime of reactor pressure vessels are practically determined by their material resistance against fast/non-ductile failure and consequently by their radiation damage resulting in irradiation embrittlement and hardening. Mechanism of irradiation embrittlement of RPV materials depends on selected materials and operation conditions but their values depend in a large extent on reactor design, i.e. on neutron flux/fluence depending on RPV wall. Generally, new RPV design allows smaller neutron fluences but absolute value of irradiation embrittlement still depends on a choice of RPV material. Even though radiation damage (especially irradiation embrittlement) is important for RPV behavior, integrity and lifetime depends, in principle, on final value of applied fracture mechanics parameter — transition temperature. Thus, its initial value as well as its shift due to irradiation embrittlement is of interest but only the embrittlement can be affected during operation.
The paper discusses absolute and relative effect of both these parameters for integrity and lifetime assessment for different type of reactors — of old and new as well as the newest design. Then, role of surveillance specimen programs for the evaluation of radiation embrittlement of RPV materials is discussed, first of all from point of view of existing codes and standards. Additionally, some recommendations are given for decreasing the effect of irradiation embrittlement on final integrity and lifetime evaluation.
The Failure Analysis and Processing of Digital Reactor Protection System
Authors: Zhao Jun , Zhou Xing , Hu Jin , Yu Yanling 
Published: February 2014

The Qinshan Nuclear Power Plant phase 1 unit (QNPP-1) has a power rating of 320 MWe generated by a pressurized water reactor that was designed and constructed by China National Nuclear Corporation (CNNC). The TELEPERM XS I&C system (TXS) is to be implemented to transform analog reactor protection system (RPS) in QNPP-1.
The paper mainly describes the function, structure and characteristic of RPS in QNPP-1. It focuses on the outstanding features of digital I&C, such as strong online self-test capability, the degradation of the voting logic processing, interface improvements and CPU security.
There are some typical failures during the operation of reactor protection system in QNPP-1. The way to analyze and process the failures is different from analog I&C. The paper summarizes typical failures of the digital RPS in the following types: CPU failure, communication failure, power failure, Input and output (IO) failure. It discusses the cause, risk and mainly processing points of typical failure, especially CPU and communication failures of the digital RPS. It is helpful for the maintenance of the system.
The paper covers measures to improve the reliability of related components which has been put forward effective in Digital reactor protection system in QNPP-1.
It will be valuable in nuclear community to improve the reliability of important components of nuclear power plants.