bluuebunny/crossref_metadata_2025_split huggingface dataset:
Protective efficacy of an IL‐12‐expressing baculoviral malaria vaccine
Authors: Iyori M. , Blagborough A. M. , Sala K. A. , Nishiura H. , Takagi K. , Yoshida S. 
Published: October 2017

SummaryInterleukin‐12 (IL‐12) plays an important role in antigen‐specific adaptive immunity against Plasmodium sporozoites, and this requirement allows for a new approach to developing an effective malaria vaccine. In this study, we examined whether IL‐12 could enhance protective efficacy of a baculovirus‐based malaria vaccine. For this aim, a baculoviral vector expressing murine IL‐12 (mIL‐12) under the control of CMV promoter (BES‐mIL‐12‐Spider) and a baculoviral vector expressing Plasmodium falciparum circumsporozoite protein (PfCSP) with post‐transcriptional regulatory element of woodchuck hepatitis virus (BDES‐sPfCSP2‐WPRE‐Spider) were generated. BES‐mIL‐12‐Spider produced bioactive IL‐12 which activates splenocytes, resulting in induction of IFN‐γ. When co‐immunized with BES‐mIL‐12‐Spider and BDES‐sPfCSP2‐WPRE‐Spider, the mouse number for high IgG2a/IgG1 ratios and the geometric mean in this group were both increased as compared with those of the other groups, indicating a shift towards a Th1‐type response following immunization with BES‐mIL‐12‐Spider. Finally, immunization with BDES‐sPfCSP2‐WPRE‐Spider plus BES‐mIL‐12‐Spider had a higher protective efficacy (73%) than immunization with BDES‐sPfCSP2‐WPRE‐Spider alone (30%) against challenge with transgenic Plasmodium berghei sporozoites expressing PfCSP. These results suggest that co‐administration of IL‐12 expressing baculoviral vector, instead of IL‐12 cDNA, with viral‐vectored vaccines provides a new feasible vaccine platform to enhance Th1‐type cellular immune responses against Plasmodium parasites.
The use of question tags in different text types of Trinidadian English
Authors: WILSON GUYANNE , WESTPHAL MICHAEL , HARTMANN JOHANNA , DEUBER DAGMAR 
Published: October 2017

ABSTRACTWe investigate the use of question tags in Trinidadian English. Using a variationist pragmatics approach and spoken material from the Trinidad and Tobago component of the International Corpus of English, we describe the distribution and pragmatic functions of variant and invariant tags across four text types. Variant question tags are rare in Trinidadian English, but a range of invariant question tags is present in the corpus. Tags serve a number of pragmatic functions, and can serve multiple functions simultaneously. Text type is a strong factor influencing the frequency of tag forms and functions, with tags associated with the local creole mainly found in informal text types.
Immediate cortical adaptation in visual and non‐visual areas functions induced by monovision
Authors: Zeri Fabrizio , Berchicci Marika , Naroo Shehzad A. , Pitzalis Sabrina , Di Russo Francesco 
Published: October 2017

Key points
Monovision is an optical correction for presbyopes that consists of correcting one eye for far distance and the other for near distance, creating a superimposition of an in‐focus with a blurred image.
Brain adaptation to monovision was studied in unexperienced observers by measuring visual evoked potentials from 64‐channels.
The first clear effect of monovision on visual evoked potentials was the C1 amplitude reduction, indicating that the unilateral blurring induced by monovision reduces feed‐forward activity in primary visual area.
Monovision led also to an increased amplitude of the P1 and pP1 components, with the latter originating in prefrontal regions. This effect probably works as an attentional compensatory activity used to compensate for the degraded V1 signal.
AbstractA common and often successful option to correct presbyopia with contact lenses is monovision. This is an unbalanced correction across the two eyes where one eye is corrected for far vision and the other eye is corrected for near vision. Monovision is therefore a form of acquired anisometropia that causes a superimposition of an in‐focus image with a blurred image. In spite of this visual anisometropia, monovision has been successfully used for many decadesl however the brain mechanism supporting monovision is not well understood. The present study aimed to measure the visual evoked potentials with a high‐density electrode array (64‐channel) in a group of presbyopes and to provide a detailed spatiotemporal analysis of the cortical activity after a short period of adaptation to monovision with contact lenses. When compared with a balanced eye near correction, monovision produced both a clear reduction of the earliest visual evoked potential components, the C1 and the N1, and an amplitude increase of the P1 and pP1. These results indicate that the unilateral blurring induced by wearing monovision contact lenses reduces feed‐forward activity in the primary visual area and feedback activity in extrastriate areas (C1 and N1 reduction). Interestingly, other brain activities in both extrastriate visual areas (the P1 component) and in the anterior insula (the pP1 component) appear to compensate for this dysfunction, increasing their activity during monovision. These changes confirm the presence of fluid brain adaptation in visual and non‐visual areas during monocular interferences.
Ups and downs of calcium in the heart
Authors: Eisner David A. 
Published: October 2017

AbstractContraction and relaxation of the heart result from cyclical changes of intracellular Ca2+ concentration ([Ca2+]i). The entry of Ca2+ into the cell via the L‐type Ca2+ current leads to the release of more from the sarcoplasmic reticulum (SR). Compared to other regulatory mechanisms such as phosphorylation, Ca2+ signalling is very rapid. However, since Ca2+ cannot be destroyed, Ca2+ signalling can only be controlled by pumping across membranes. In the steady state, on each beat, the amount of Ca2+ released from the SR must equal that taken back and influx and efflux across the sarcolemma must be equal. Any imbalance in these fluxes will result in a change of SR Ca2+ content and this provides a mechanism for regulation of SR Ca2+ content. These flux balance considerations also explain why simply potentiating Ca2+ release from the SR has no maintained effect on the amplitude of the Ca2+ transient. A low diastolic [Ca2+]i is essential for cardiac relaxation, but the factors that control diastolic [Ca2+]i are poorly understood. Recent work suggests that flux balance is also important here. In particular, decreasing SR function decreases the amplitude of the systolic Ca2+ transient and the resulting decrease of Ca2+ efflux results in an increase of diastolic [Ca2+]i to maintain total efflux.
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Relationship Between Threshold Current Density of Electromigration Damage Considering Void and Hillock Formation and Reservoir Shape in Interconnect Line
Authors: Takaya Ryuji , Sasagawa Kazuhiko , Fujisaki Kazuhiro , Moriwaki Takeshi 
Published: October 2017

Reservoir structures are often constructed in the interconnection to prevent the electromigration damages. In this study, a numerical simulation technique for analyzing the atomic density distributions in the line under high current density was used to evaluate the effects of reservoir length and location on the threshold current density considering void and hillock generations.
The threshold current density is determined when the local atomic density in the line reaches the upper critical value for hillock creation or the lower critical value for void generation. Atomic density distributions in the line were simulated when cathode and anode reservoir lengths were changed.
The threshold current density considering void formation became higher with longer cathode reservoir and shorter anode reservoir. However, opposite results obtained in the case of hillock formation. It was found that there was an optimum value of reservoir length, corresponding to both critical values of hillock and void initiation.
Comparison and Evaluation of Different Monitoring Methods in a Data Center Environment
Authors: Tradat M. , Khalili S. , Sammakia B. , Ibrahim M. , Peddle Th. , Calder A. , Dawson B. , Seymour M. , Nemati K. , Alissa H. 
Published: October 2017

The operation of today’s data centers increasingly relies on environmental data collection and analysis to operate the cooling infrastructure as efficiently as possible and to maintain the reliability of IT equipment. This in turn emphasizes the importance of the quality of the data collected and their relevance to the overall operation of the data center. This study presents an experimentally based analysis and comparison between two different approaches for environmental data collection; one using a discrete sensor network, and another using available data from installed IT equipment through their Intelligent Platform Management Interface (IPMI). The comparison considers the quality and relevance of the data collected and investigates their effect on key performance and operational metrics. The results have shown the large variation of server inlet temperatures provided by the IPMI interface. On the other hand, the discrete sensor measurements showed much more reliable results where the server inlet temperatures had minimal variation inside the cold aisle. These results highlight the potential difficulty in using IPMI inlet temperature data to evaluate the thermal environment inside the contained cold aisle.
The study also focuses on how industry common methods for cooling efficiency management and control can be affected by the data collection approach. Results have shown that using preheated IPMI inlet temperature data can lead to unnecessarily lower cooling set points, which in turn minimizes the potential cooling energy savings. It was shown in one case that using discrete sensor data for control provides 20% more energy savings than using IPMI inlet temperature data.
Application of Computed Tomography for the Examination of Pressure Retaining Nuclear Plant Components
Authors: Gratton Robert , Wilson James , Skuse Kevin 
Published: October 2017

Pressure retaining nuclear plant components require high levels of quality assurance to support the rigorous requirements of the modern safety case and the ASME Boiler and Pressure Vessel Code. Part NB-2500 of the ASME BPVC requires 100% volumetric examination of pressure retaining components and attachment welds utilising suitably demonstrated ultrasonic and radiographic examination techniques respectively. The capability of the inspection technique is particularly important for thin-walled components where the typical size of manufacturing defects tend to make up a greater proportion of the wall thickness.
Computed Tomography (CT) is a development of conventional radiography and makes use of computer-processed combinations of many X-ray images taken from different angles to produce cross-sectional images of specific areas of a scanned object. This technique can be used to compliment and add strength to the standard volumetric examinations; ie the detection capability for conventional radiography is often dependent on alignment of the source to defect and ultrasonic methods are more suited to targeting planar flaws.
Rather than the technical challenges placed on the Non-Destructive Examination (NDE) practitioner, this paper focuses on the benefits of application of CT to thin-walled nuclear plant components from the viewpoint of the nuclear plant component Design Engineer.
The CT examples presented in this paper demonstrate reliable detection of voids measuring 4% of thickness including those located at features which are difficult to examine using standard techniques. These CT examinations compliment the standard volumetric inspections and provide high confidence that the component is free of structurally significant defects.
Embrittlement Trend Curves for Notch and Fracture Toughness of 15Kh2MFAA Type Steel
Authors: Brumovsky Milan , Kopřiva Radim , Kytka Miloš 
Published: October 2017

Reactor pressure vessel integrity and lifetime evaluation is based on the use of fracture mechanics apparatus but most of the material vessel material data and their degradation during operation are based on results from Charpy V-notch impact tests. Then, empirical correlations between transition shift of temperature dependence of notch toughness and fracture toughness are applied.
Elaboration of „Master Curve“ approach for fracture toughness experimental data analysis allows to use fracture toughness data directly to the reactor pressure vessel integrity evaluation. Wider use of this approach is limited by the lack of appropriate database from surveillance specimen test data, as mostly only Charpy impact specimen are included into the Surveillance specimen programs. Fortunately, all WWER Surveillance programs contain also fracture toughness specimens, either pre-cracked Charpy size or CT-0.5.
Thus, database of fracture toughness data from Surveillance programs of WWER-440/V-213C type reactor pressure vessels, operated in the Czech Republic, Slovakia and Hungary and manufactured only by one manufacturer - SKODA JS, was collated and analyzed.
These vessels were manufactured from 15Kh2MFAA type steel and appropriate weld metal, both of Cr-Mo-V type with low content of detrimental impurities — P and Cu. Analysis of the data in fluence interval up to 6×1024 m−2 (with neutron energies En larger than 0.5 MeV) show that transition temperature shifts in fracture toughness temperature dependence are higher than for Charpy impact tests.
Several formulae have been applied for fitting these shift dependencies with chemical composition of materials and finally new Embrittlement Trend Curves for Charpy shifts have been corrected. Additionally, new Embrittlement Trend Curves for fracture toughness shifts based on “Master Curve” approach have been also proposed. Both trends are using simple power law on fluence with exponents around 0.6 and depend on phosphorus and copper contents even though effect of other elements has been also checked.
Remaining Life Assessment of an External Pressure Vessel in Creep Range and Inspection Findings
Authors: Ishizaki Yoichi , Yonekawa Futoshi , Yumoto Takeaki , Suzuki Teppei , Hijikawa Shuji 
Published: October 2017

As widely recognized in the industry, it is important to evaluate the creep damage of an elevated temperature vessel so that the mechanical integrity of the vessel can be achieved through the adequate repair and replacement planning. This is quite straight forward procedure for internal pressure vessels.
For an external pressure vessel, it is not easy to assess the creep damage due to the complexity of the creep buckling analysis. Eventually, creep cavity evaluation technique without identifying the correct stress distribution has been used so often. However, due to the uncertainty of the technique itself plus conservative mindset of the inspectors, it tends to leads to an excessive maintenance most of the cases. In order to conduct a reasonable remaining life assessment, it is desirable to use the creep cavity inspection in conjunction with another assessment technique such as FEM creep analysis as stated in API 579-1/ASME FFS-1 10.5.7.
In this paper, comprehensive approach with FEM and field inspection such as creep cavity evaluation to reinforce the uncertainty of each method will be demonstrated.
Closed-Form Stress Intensity Factor Solutions for Deep Surface Cracks in Cylinders Subjected to Global Bending
Authors: Azuma Kisaburo , Li Yinsheng , Hasegawa Kunio , Shim Do Jun 
Published: October 2017

Materials made of alloy 82/182/600 used in pressurized water reactors are known to be susceptible to primary water stress corrosion cracking. The depth, a, of flaws due to primary water stress corrosion cracking can be larger than half of the crack length c, which is referred to as cracks with large aspect ratios. The stress intensity factor solution for cracks plays an important role to predict crack propagation and failure. However, Section XI of the ASME Boiler and Pressure Vessel Code does not provide the solutions for cracks with large aspect ratio.
This paper presents the stress intensity factor solutions for circumferential surface cracks with large aspect ratios in cylinders under global bending loads. Finite element solutions were used to fit closed-form equations with influence coefficients Ggb. The closed-form solutions for coefficient Ggb were developed at the deepest points and the surface points of the cracks with aspect ratio a/c ranged from 1.0 to 8.0.
The Effectiveness of Non-Loosening Fasteners
Authors: Shoji Yasumasa 
Published: October 2017

Many people know that bolted fasteners are loosened and they sometimes suffer from the loosening. It is also the case for any plants who have hundreds of thousands of bolts.
Any of these bolts may cause serious problems when they are loosened.
Many countermeasures are proposed to prevent bolt loosening, but few of them are really effective.
So far, only three bolting systems passed NAS 3350 tests. They are Eccentric nuts, based on nut eccentricity, Lock’n bolt, based on outer expansion of bolt threads, and L/R nut, whose principle is not open.
As L/R nut is unknown how it works, this paper addresses the effectiveness of the Eccentric nuts and Lock’n bolts and compare them in simulation.
The author have been working in bolt system loosening for a long time and succeeded the simulation of the phenomenon. This paper is the continuous work of this research.
ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects
Authors: Klasky Hilda B. , Bass B. Richard , Dickson Terry L. , Gorti Sarma B. , Nanstad Randy K. , Sokolov Mikhail A. , Server William L. , Williams Paul T. 
Published: October 2017

The Oak Ridge National Laboratory (ORNL) performed a detailed technical review of the 2015 Electrabel (EBL) Safety Cases prepared for the Belgium reactor pressure vessels (RPVs) at Doel 3 and Tihange 2 (D3/T2). The Federal Agency for Nuclear Control (FANC) in Belgium commissioned ORNL to provide a thorough assessment of the existing safety margins against cracking of the RPVs due to the presence of almost laminar flaws found in each RPV. Initial efforts focused on surveying relevant literature that provided necessary background knowledge on the issues related to the quasi-laminar flaws observed in D3/T2 reactors. Next, ORNL proceeded to develop an independent quantitative assessment of the entire flaw population in the two Belgian reactors according to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Appendix G, “Fracture Toughness Criteria for Protection Against Failure,” New York (both 1992 and 2004 versions). That screening assessment of the EBL-characterized flaws in D3/T2 used ORNL tools, methodologies, and the ASME Code Case N-848, “Alternative Characterization Rules for Quasi-Laminar Flaws”.
Results and conclusions derived from comparisons of the ORNL flaw acceptance assessments of D3/T2 with those from the 2015 EBL Safety Cases are presented in the paper. The ORNL screening analyses identified fewer flaws than EBL that were not compliant with the ASME Section XI (1992) criterion; the EBL criterion imposed additional conservatisms not included in ASME Section XI. Furthermore, ORNL’s application of the updated ASME Section XI (2004) criterion produced only four non-compliant flaws, all due to design-basis loss-of-coolant loading transients. Among the latter, only one flaw remained non-compliant when analyzed using the warm-prestress (WPS) cleavage fracture model typically applied in USA flaw assessments. ORNL’s independent refined analysis of that flaw (#1660, which was also non-compliant in the EBL screening assessments) rendered it compliant when modeled as a more realistic individual quasi-laminar flaw using a 3-dimensional XFEM (eXtended Finite Element Method) approach available in the ABAQUS© finite element code. Taken as a whole, the ORNL-specific results and conclusions confirmed the structural integrity of Doel 3 and Tihange 2 under all design transients with ample margin in the presence of the 16,196 detected flaws.
Investigation of Leakage Rates in Pressure Retaining Piping
Authors: Silber Fabian E. , Schuler Xaver , Weihe Stefan , Laurien Eckart , Kulenovic Rudi , Schmid Stefan , Heckmann Klaus , Sievers Jürgen 
Published: October 2017

Within the break preclusion concept, leak-before-break (LBB) behavior must be demonstrated for safety relevant pressure retaining piping systems in nuclear power plants (NPP) [1]. This requires leak detection systems in NPP with the capability to detect leak rates below the maximum allowable leak rate calculated by the LBB assessment according to nuclear standards, like the German KTA rule 3206 or the U.S. Standard Review Plan (SRP). An important part of the LBB assessment is the availability of accurate calculation models to predict the leak rate under normal operating conditions for postulated through wall cracks. Current leak detection systems in NPP are capable of reliably detecting liquid leak rates 0.05 kg/s. However, most of the available experimental leak rate data published in literature focus on the range between 0.2 kg/s and 2 kg/s, which is significantly above the detection limit. Therefore, additional experimental investigations are necessary to develop and verify leak rate calculation models for smaller leaks.
In order to investigate such types of leaks, a modular test facility (fluid-structure-interaction test loop) has been developed and installed at MPA University of Stuttgart within the framework of a research project sponsored by the German Ministry of Education and Research (BMBF). The test rig includes a leakage piping module which includes artificially machined slits and fatigue through-wall cracks. It allows the variation of the significant influencing parameters such as crack size, surface roughness and the system parameters pressure and temperature up to 75 bar and 280 °C and also the measurement of the pressure gradient across the crack surface at two locations. This is important to develop a better understanding of the two-phase flow and pressure drop across the leak channel.
A first test series has been performed and the results were used to evaluate existing leak-rate models. Within this paper an overview of the test facility, the testing procedure, and the results of the investigations will be presented and discussed.
Effects of Finite Strains and Residual Stresses on Path Independence of the J-Integral for Ductile Cracks
Authors: Zhu Xian-Kui , McGaughy Tom 
Published: October 2017

Large plastic deformation and residual stresses exist in mechanical damages to pipelines. If a crack occurs in the damages, residual stresses will affect mechanics behavior of the crack and path independence of the J-integral, and so the J-integral may lose capacity to describe fracture driving force.
This paper theoretically investigates basic conditions required for the path independence of the J-integral and major factors affecting the path independence, including the incremental plasticity, finite strains and residual stresses. Residual stress modified J-integrals are then introduced for ensuring the path independence. With use of a notched beam, detailed elastic-plastic finite element analyses are performed in terms of the incremental plasticity for a crack subject to three-point bending. The path dependence of the J-integral due to the three major factors is then evaluated. Numerical results show that the residual stress modified J-integral is path-independent, and able to describe the fracture driving force for ductile cracks in a residual stress field. This provides a new technology to assess pipeline integrity for cracks coupling residual stresses.