bluuebunny/crossref_metadata_2025_split huggingface dataset:
Allelopathic disruptions of biotic interactions due to non-native plants.
Authors: Smith-Ramesh Lauren M. 
Published: December 2020

Abstract

Allelopathy, or the process by which plants influence the growth and performance of their neighbours through the release of chemicals, may play a key role in mediating the impacts of non-native invasive species on their neighbours. The Novel Weapons Hypothesis purports that non-native invasive species are in part successful because they produce harmful allelochemicals to which resident species are particularly susceptible because residents lack a shared evolutionary history with the invader. While allelopathic non-native invaders may reduce the growth and performance of neighbours through direct phytotoxicity, they may more often exert negative impacts through disruption of biotic interactions among resident species. Allelopathy by non-native plants may disrupt mutualisms between resident plants and microbes, plant-herbivore interactions or existing competitive and facilitative interactions among resident plants. For example, several non-native plants are known to disrupt the mutualism between resident plants and mycorrhizal fungi, reducing resident plant fitness to the benefit of the invader. Allelopathic non-natives may also disrupt interactions among resident plants and their herbivores when allelochemicals also influence herbivore behaviour or fitness. Alternatively, biotic interactions can also be protective for resident species, which may be less susceptible to the impacts of non-native species when their mutualisms are intact. As we advance our understanding of allelopathy and its role in mediating the impacts of invasive plant species, we may gain new insights by viewing invasions within a network context rather than focusing on pairwise interactions.
Restoration of seed dispersal interactions in communities invaded by non-native plants.
Authors: da Silva Fernanda Ribeiro , Pizo Marco Aurélio 
Published: December 2020

Abstract

Restoration aims to rebuild not only species but also the tangled interactions between species that ensure communities perpetuate by themselves. In tropical forests, restoration of seed dispersal interactions is essential because most plant species depend on animals to spread their seeds. A big challenge in restoring such forests is dealing with invasion by non-native species. Non-native plant species may outcompete and eliminate native species from the community, potentially disrupting or arresting the restoration process. Once established, invasive non-native plants are usually incorporated into the local seed dispersal network, potentially causing loss of biodiversity by competition with native species. This chapter reports on a case study of a 25-year old restored forest invaded by several bird-dispersed plant species. We assessed network metrics at the species level to specifically evaluate the role performed by invasive non-native species in the structure of the bird - seed dispersal network. The removal of invasive non-native plants and the re-establishment of native plant communities should be considered for the restoration of habitats invaded by non-native plants. For this reason, we discuss the impacts of removing such non-native plants and explore the consequences for the structure of the overall network. Because restoration areas are open systems, even after the removal of invasive non-native plant species they can return via seed dispersal. So, both the control and management of invasive non-native species would be more effective if planned with a landscape perspective. We also point out relevant management aspects to avoid the negative influence of invasive non-native plants on the seed dispersal interactions occurring between native plant and bird species in restored tropical forests.
Hysteresis-free MoS2 metal semiconductor field-effect transistors with van der Waals Schottky junction
Authors: Wan Da , Wang Qixia , Huang Hao , Jiang Bei , Chen Chen , Yang Zhenyu , Li Guoli , Liu Chuansheng , Liu Xingqiang , Liao Lei 
Published: December 2020

Abstract
Hysteresis-free and steep subthreshold swing (SS) are essential for low-power reliable electronics. Herein, MoS2 metal semiconductor field-effect transistors are fabricated with GeSe/MoS2 van der Waals Schottky junction as a local gate, in which the rectification behavior of the heterojunction offers the modulation of channel carriers. The trap-free gate interface enables the hysteresis-free characteristics of the transistors, and promises an ideal SS of 64 mV/dec at room temperature. All the devices operate with a low threshold voltage less than −1 V with desirable saturation behavior. An OR logic gate is constructed with the dual-gated MoS2 transistors by varying the back and top gate voltage. The strategy present here is promising for the design of low-power digital electronics based on 2D materials.
Stochastic models of systems for Nanotechnology: from micro to macro scale
Authors: Longo Savino , Micca Longo Gaia , Hassouni Khaled , Michau Armelle , Prasanna Swaminathan 
Published: December 2020

Abstract
Computer modeling technique based on the theory of stochastic processes have been used in order to provide a realistic simulation of the behavior of nanoscopic systems, related in particular to plasma reactors in microelectronic device production. Basing on decades of experience, we show here, with new results, that the universality of such methods allows the development of codes with the highest reusability and versatility, crossing the barrier of scale. At the smallest scale, the quantum calculations of the potential energy surface of hydrogen species under nano-confinement conditions display the effects due to the dimension and the symmetry of the confining potential well. At a slightly larger scale, nanoparticles dispersed as aerosol in plasma feature strong fluctuations in temperature and charge which may affect the processing of silicon wafers. At the macroscopic scale, using a stochastic solution of transport equations, it is possible to describe laboratory or industrial systems for the production or treatment of nanomaterials, also exploiting the analogy between neutral particle transport and radiative transfer and information obtained by molecular simulations. These findings are relevant in the control of solid-particle contamination in the manufacture of electronic components and in other fields.
Ginzburg Landau equation's Innovative Solution (GLEIS)
Authors: Achab Abdelfattah EL , Rezazadeh Hadi , Baleanu Dumitru , Desta Leta Temesgen , Javeed Shumaila , Alimgeer Khurram Saleem 
Published: December 2020

Abstract
A novel soliton solution of the famous 2D Ginzburg-Landau equation is obtained. A powerful Sine-Gordon expansion method is used for acquiring soliton solutions 2D Ginzburg-Landau equation. These solutions are obtained with the help of contemporary software (Maple) that allows computation of equations within the symbolic format. Some new solutions are depicted in the forms of figures. The Sine-Gordon method is applicable for solving various non-linear complex models such as, Quantum mechanics, plasma physics and biological science.
Unsupervised fNIRS feature extraction with CAE and ESN autoencoder for driver cognitive load classification
Authors: Liu Ruixue , Reimer Bryan , Song Siyang , Mehler Bruce , Solovey Erin 
Published: December 2020

Abstract

Objective. Understanding the cognitive load of drivers is crucial for road safety. Brain sensing has the potential to provide an objective measure of driver cognitive load. We aim to develop an advanced machine learning framework for classifying driver cognitive load using functional near-infrared spectroscopy (fNIRS). Approach. We conducted a study using fNIRS in a driving simulator with the N-back task used as a secondary task to impart structured cognitive load on drivers. To classify different driver cognitive load levels, we examined the application of convolutional autoencoder (CAE) and Echo State Network (ESN) autoencoder for extracting features from fNIRS. Main results. By using CAE, the accuracies for classifying two and four levels of driver cognitive load with the 30 s window were 73.25% and 47.21%, respectively. The proposed ESN autoencoder achieved state-of-art classification results for group-level models without window selection, with accuracies of 80.61% and 52.45% for classifying two and four levels of driver cognitive load. Significance. This work builds a foundation for using fNIRS to measure driver cognitive load in real-world applications. Also, the results suggest that the proposed ESN autoencoder can effectively extract temporal information from fNIRS data and can be useful for other fNIRS data classification tasks.
Liquid metal flat jet transformation under influence of transverse magnetic field
Authors: Pyatnitskaya N , Luchinkin N , Belyaev I , Kolesnikov Yu , Krasnov D , Listratov Ya , Zikanov O , Sviridov E 
Published: December 2020

Abstract
The article is devoted to an experimental study of a submerged flat jet flow in a transverse magnetic field. Two different approaches to the experimental study of jet flows are described. Detailed information about the experimental program and measuring methods presented here. The flow of a flat jet 6 mm high in a square channel with a side of 56 mm is considered. The channel is positioned so that the plane of the jet is perpendicular to the magnetic field induction. The results of measuring velocity profiles and waveforms by swivel-type probe with potential sensor are presented. Effects that can be interpreted in different ways are found: strongly unstationary flow regimes, mean flow reorganization, and development of near-wall jets. Additional experiments are prepared to obtain more detailed information about the restructuring and development of the jet. In particular, continuous measurements along the channel will be made in the presence of a slight main flow.
Accounting for Uranium-234 During the Analysis of Experiments at the Research Fast Reactor with High Enrichment
Authors: Kotov Ya A , Nevinitsa V A , Smirnov A Yu 
Published: December 2020

Abstract
Paper is an attempt to consider the influence of U-234 presence through the comparison of the calculated assessments of the temperature reactivity effect (TRE) and the sodium void reactivity effect (SVRE) of the fast research reactor CEFR with 64.4% enrichment on U-235 isotope and measured values of the temperature reactivity effect and sodium void reactivity effect. Additional investigation was performed to account for U-234 in the first criticality experiment. Experimental data are provided in frames of IAEA Coordinated Research Project “Neutronics Benchmark of CEFR Start-Up Tests”. The content of U-234 was calculated by us using mathematical model of the quasi-ideal enrichment cascade. Due to the high enrichment, the content of U-234, although still small, has ceased to be vanishingly small. The effect caused by this isotope is appeared not only through the presence of new isotope in the fuel load, but also in a decrease in the mass of the U-238 isotope in the fuel load. It is shown, that accounting for U-234 slightly increases the agreement of the calculated assessments of TRE among themselves (values of deviation shifted toward each other)/Also accounting for the U-234 isotope leads to a small but systematic increase in the values of the effective multiplication factor by 120-150 pcm.
Analysis of beyond design basis accident with hydrogen explosion in the at-reactor spent fuel storage pool of NPP with RBMK-1000
Authors: Gryazev A S , Osipov A M , Finoshkina D V , Tupotilov I A 
Published: December 2020

Abstract
The article evaluates the consequences of a hydrogen explosion in an at-reactor spent fuel storage pool due to the development of a beyond design basis accident with a complete long-term blackout. Two scenarios of hydrogen generation in a spent fuel storage pool with a subsequent hydrogen explosion are considered. In the first scenario, the formation of radiolytic hydrogen occurs in the undried storage pool. In the second scenario, hydrogen is formed as a result of the steam-zirconium reaction in the dried storage pool when the cooling water is supplied to the walls of the emergency storage pool. The maximum explosion pressure is calculated using the shock Hugoniot adiabat. The calculations of initial static load taking into consideration hydrogen explosion exposure for each scenario were performed using the equivalent static load method. This method consists in the switch from a dynamic task to a static one, in which the maximum deflections are equivalent. The calculation of the stress-strain state of spatial structures is carried out in the ZENIT-95 program. It is shown in the work that not in all cases of hydrogen explosion, destruction of structures occurs.
New finite element neutron kinetics coupled code system FENNECS/ATHLET for safety assessment of (very) Small and Micro Reactors
Authors: Bousquet J , Seubert A , Henry R 
Published: December 2020

Abstract
Cores of (very) small and medium size reactor–(v)SMR – are often characterized by irregular geometries. Monte Carlo methods are not yet mature enough for transient applications. To perform coupled transient safety assessments of (v)SMRs, the Finite ElemeNt NEutroniCS (FENNECS) code is being developed at GRS. It solves the time-dependent and steady-state three-dimensional few-group diffusion equation in Galerkin finite element representation using upright triangular prisms with linear basis functions as spatial elements. FENNECS is also coupled with the GRS thermal-hydraulic system code ATHLET. For the special meshing, an external meshing tool is being developed as a Python software module. This paper considers the Heat Pipe Micro Reactor core. For the generation of cross sections to be used in FENNECS, Monte Carlo Serpent models are developed for two configurations: all absorber faces of control drums are turned out of the core (All Rods Out – ARO – configuration) and all absorber faces are turned in (All Rods In – ARI – configuration). The Serpent multiplication factors are in good agreement with the benchmark. In the FENNECS model, control drums are approximated by a 12-edges polygon or by a 24-edges polygon. The FENNECS multiplication factors agree well with Serpent reference results for both configurations. This demonstrates the applicability of FENNECS to (v)SMRs.
Radioactive waste management in PWR technology: some technical solutions for liquid radioactive media processing systems of the “nuclear island”
Authors: Vinnitskii V A , Chugunov A S 
Published: December 2020

Abstract
The present research is aimed at solving an urgent practical problem – to minimize the volume of the radioactive waste from nuclear power plants in the place of their generation. The modernization of the complexes for handling water streams containing radionuclides seems to be the most acceptable solution. The systems developed in the 1960s for the chemical support of the safe operation of the reactor plant and the radioactively contaminated water processing no longer meet the established requirements, primarily in terms of the volume and quality of radioactive waste subject to “eternal” isolation. The search for a reasonable compromise between the amount of waste generated during the operation of systems to ensure the safe operation of nuclear power plants and the theoretically achievable volume of radioactive waste can be considered as the current agenda. The ratio between these indicators will shift as the material and technical base of the available materials and devices is steadily improving, the base itself has significantly expanded over the past time. In this regard, the most urgent is the change in methodological approaches to the organization of chemical technological systems of NPP. First of all, this refers to the advisability of abandoning universal systems in favor of specialized ones adapted to the chemical composition of the processed “raw material”. Separate collection of liquid radioactive waters basing on the principle of chemical composition similarity will allow to use low productivity systems. In this case, local systems can be used only once. The article presents some approaches to the organization of systems capable of providing a radical reduction in the intake of ballast salts in the composition of radioactive waste.
Possibilities and Features of REMIX Technology as an Initial Stage in the Establishing of a Full-Scale Two-Component Nuclear Energy System
Authors: Sitdikov E R , Vasilenko A V , Diachenko A I 
Published: December 2020

Abstract
According to the Energy Strategy of Russia for the period up to 2035, the direction of the transition of the nuclear industry is to be headed to a two-component nuclear energy system (NES. In this paper, in order to identify the features of recycling MOX and REMIX fuel and to analyze possible strategies for two-component NES, the changes in the isotopic composition of the plutonium fraction during multiple recycling of fuel has been evaluated, and the consumption of plutonium in various strategies of establishing a two-component NES has been quantitatively assessed. The data obtained can be used for the further analysis of the possibility of developing the two-component NES concept with the involvement of REMIX fuel in the nuclear fuel cycle of thermal reactors at the initial stage of the establishing of a full-scale two-component NES.
Hand-foot monitors for nuclear plants based on scintillator–WLS–SiPM technology
Authors: Buzhan P , Karakash A 
Published: December 2020

Abstract
The technology of charged particles detection by a plastic scintillator light from which is collected by wavelength shifting fiber (WLS) on Silicon Photomultiplier (SiPM) is widely used in high energy physics. We present in this article the new personnel surface contamination monitoring assembly based on that technology as a result of about two years R&D research. This assembly is used for contamination control of hands, feet and clothes at nuclear power plants, nuclear facilities and other objects that work with radioactive materials. Setup design, main parameters and its measurement procedures are presented. It has high efficiency to α and β particles in wide energy range, large dynamic range, very good area uniformity and excellent temperature stability. Dynamic range of measured particle fluence rate equals: 1 – 106 Hz·cm2·min for β-module and 0.1 – 2·104 Hz·cm2·min for α-module. Variations of the module response in temperature range from –20 C up to +50 C doesn`t exceed 3%.
Computer technologies in the system of training specialists for the nuclear industry at ISPU
Authors: Gorbunov V A , Ilchenko A I , Andrianov S G , Mechtaeva M N , Volman M A 
Published: December 2020

Abstract
The article discusses the experience of effective application of computer technologies, trainers and simulators in the system of training specialists for the nuclear industry at ISPU. The necessity and relevance of using computer-based learning tools in the educational process is determined. The main stages of training specialists and the concept of multi-level training based on the wide use of computer technologies developed at ISPU are considered. The main advantages and features of using automated training systems, local computer simulators, functional analytical simulator, full-scale simulator, simulation tools, simulator of the basic principles of NPP operation, as well as packages of numerical and analytical methods of mathematical modeling in the educational process are shown. The directions for further improvement of the educational process at ISPU in order to increase the level of training of young personnel for the nuclear industry are shown.
The Modeling of kinetic characteristics of subcritical assembly “Yalina” using SuperMC Monte Carlo code
Authors: Zubets I A , Korbut T N , Kravchenko M O 
Published: December 2020

Abstract
Accelerator-driven systems (ADS) are considered to be promising for energy generation and transmutation of the long-live radiotoxic nuclides contained in spent nuclear fuel. The Yalina assembly has the same conceptual construction with a neutron generator coupled to a subcritical core. The major difference between ADS and Yalina experiments is that the neutron energy spectrum of the Yalina core is thermal. The simulation of the Yalina-Thermal experimental program was conducted via new neutron-physics code SuperMC developed by the FDS Team in China. SuperMC is a CAD-based Monte Carlo program for integrated simulation of nuclear systems by making use of hybrid Monte Carlo and deterministic methods and advanced computer technologies. The calculations were held with the use of the up to date nuclear data libraries ENDF/B-VII.1, ENDF/B-VIII, FENDL 3.0, JEFF 3.3, JENDL 4.0. The effective multiplication constant, keff, and the fraction of delayed neutrons, βeff, were calculated for the 285 fuel rod core configuration of the Yalina-Thermal subcritical assembly. Evaluation of the Yalina-Thermal experimental program using SuperMC code has been made for the first time in this work.
Estimation of pressure during steam explosion in the sub-reactor room of NPP with RBMK-1000
Authors: Finoshkina D V , Melikhov O I , Osipov A M 
Published: December 2020

Abstract
The article analyzes the scenario of a severe beyond the design basis accident with core melting at a nuclear power plant with RBMK-1000. Molten reactor core falls into the sub-reactor space filled with a steam-water mixture. The interaction of melt core and the coolant can lead to the creation of conditions for the occurrence of a steam explosion. Parameters of this steam explosion have been evaluated by Hugoniot adiabat method. Such approach considers the steam explosion as detonation phenomenon, where shock wave impacts initial multiphase mixture and initiates melt droplets fragmentation and high heat flux from melt to water. Mass, momentum and energy conservation equations for initial mixture and for equilibrium explosion products mixture lead to Hugoniot equation for the adiabat. The tangent from initial point (initial mixture) on the plane “mixture volume-mixture pressure” to the Hugoniot adiabat determines Chapman – Jouguet point, which characterizes steam explosion parameters. Our calculations have demonstrated that obtained values of steam explosions do not exceeds dangerous limits.
Estimation of the influence of elastic neutron scattering anisotropy on the integral parameters of the model experiment
Authors: Zhukov V D , Listov A S , Pronyaev V G , Sinitsa V V 
Published: December 2020

Abstract
For the vast majority of isotopes presented in modern evaluated data libraries, the quality of description of elastic neutron scattering anisotropy is difficult to assess due to the lack of critical experiments that are sensitive to these data. This results in a large variation in these data, due to both the difference in the models used in the estimation, and the smoothing of the resonance peculiarities in representation of the energy dependence in the evaluated data files. This work estimates the effect of anisotropy of elastically scattered neutrons based on the model of a critical assembly with a reflector from the tested isotope. Direct estimates of the angular distributions in the evaluated data libraries were compared with the angular distributions, which were reconstructed from the resonance parameters by using Blatt-Biedenharn formula. The thickness of the reflector at which an assembly model became critical is used as a comparison value. The obtained integral characteristics of the elastic scattering anisotropy data, together with the performed comparisons of the detailed dependences of the angular distribution parameters, can serve as a basis for setting tasks to improve the quality of the evaluated data.