bluuebunny/crossref_metadata_2025 huggingface dataset:
Factors Influencing the Improvement of Students’ Communication Skill: An Industrial Training Intervention
Authors: Azreen Rodzala Shazaitul , Mohamed Saat Maisarah
Published: February 2019

Communication skill has been globally recognized as among required attributes for graduates employability. This situation urges the stakeholders to find ways in preparing students with excellent communication skill. An implementation of iCGPA in public universities is one of recent initiatives taken by Ministry of Education with the aims to produce graduates who are balanced in both academics and non-academics. Undergoingindustrial training also is a good platform for students to improve their communication skillas they being exposed to hands-on-work. Thus, this paper aims to examine students’ communication skill improvement based on industrial training intervention. It also aims to examine the relationship between communication skill improvement and selected factors, and further explore the predictors of this improvement. A quantitative method using pre and post survey was adopted. The survey was conducted among undergraduate students from six different public universities in Malaysia. Overall, findingsof paired sample t-test reveal that students’ communication skill improvement has developed significantly after undergoing industrial training. The improvement were found to be correlated with program of study, motivation, leadership styles and organizational cultures. Using multiple regression analysis;extrinsic motivation, low power distance culture, medium size of organization and laissez-faire leadership style are the best predictor of communication skill improvement.
Problems in Validation of the Chornobyl Accident Initiating Event
Authors: Sharaievskii G.
Published: February 2019

The paper presents validation of known calculation dependencies used in RELAP-5 and other advanced computer codes to predict thermohydraulic anomalies from the standpoint of analyzing effect of initial coolant boiling in the Chornobyl accident on its further progression. The authors show current unsatisfactory efficiency of state-of-the-art computer codes in definition of the initial boiling point for the coolant in water-cooled nuclear reactors. The calculation methodology for improving accuracy in the predicting of dangerous thermal anomaly in reactor channels is under consideration.
Shelter – from Sarcophagus to New Safe Confinement
Authors: Domnikov V. , Dybach O. , Kilochytska T. , Kondratiev S. , Kutina I. , Kutina L. , Nosovsky A. , Rybalka N. , Skliarenko V. , Sushko T.
Published: February 2019

In the frameworks of the international Action Plan for the Chornobyl Shelter, the experts analyzed experience in safety regulation of the efforts on overcoming consequences of the accident that occurred 30 years ago at ChNPP-4 and presented achievements under this Plan.
Results of the Project “Analysis of Environmental Risk in the Exclusion Zone at the Belarus-Ukraine Border”
Authors: Kutonova T. , Kireev S.
Published: February 2019

Results of the Project “Analysis of Environmental Risk in the Exclusion Zone at the Belarus-Ukraine Border”
Supercritical Extraction by Carbon Dioxide of Uranium from Ore Concentrates and Low-Enriched Ores of Tailing
Authors: Borts B. , Ivanova S. , Koliabina I. , Lysychenko G. , Tkachenko V.
Published: February 2019

The extraction and processing of uranium ores in Ukraine have led to the accumulation of large amounts of waste. It is obvious that the old technologies are not applicable to the extraction of uranium from such waste. Therefore, the search for the new, more efficient methods of extracting residual amounts of waste nutrients and subsequent improvement of the environmental status of contaminated areas are both necessary. The supercritical carbon dioxide fluid extraction (SFE-CO2) is proposed as a method that can be utilized independently or as the last step of the acid leaching method adopted at VostGOK to extract the uranium. The efficiency of uranium SFE-CO2 can reach 98%.
Application of RELAP5/MOD3.2 Cladding Deformation Model for VVER-1000 Fuel in Design-Basis Accident Analysis
Authors: Vorobyov Yu. , Zhabin O. , Frankova M.
Published: February 2019

The paper presents applicability of built-in RELAP5/MOD3.2 cladding deformation model for VVER-1000 fuel with cladding of Zr+1 % Nb alloy. Experimental data and simplified model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the hot channel blockage after cladding swelling and rupture in the interval of temperatures from 600 to 1200°С and interval of pressures from 1 to 12 MPa. It is demonstrated that RELAP5/MOD3.2 builtin model of cladding deformation can be applied to VVER-1000 cladding of Zr+1%Nb alloy rupture estimation only in the certain limited range of parameters. The analysis of RELAP5/MOD3.2 cladding deformation model parameters influence on the peak cladding temperature in double-ended cold leg break was performed. The paper presents recommendations on the use of RELAP5/MOD3.2 built-in cladding deformation model in the design basis accident analysis of VVER-1000 reactors.
Methodology for Determination of Initial Boiling Point in Fuel Assemblies by Acoustic Noise Analysis
Authors: Sharaievskyi G.
Published: February 2019

The paper justifies the need for considering differences in physical conditions to define vapour phase initiation in various types of thermohydraulic cells of fuel assemblies. The computer analysis of coolant boiling conditions was performed based on available computer dependencies. The research defines significant differences in calculation of heat flow values regarding vapour phase initiation for piping and fuel assemblies. An efficient algorithm of neurocomputing analysis of acoustic noise spectrum was proposed and implemented to detect the initial boiling point.
Experience of Implementation of Safety and Normal Operation Control Systems at NPP Units
Authors: Yelisieiev V. , Pyvovarov G. , Herasymenko K.
Published: February 2019

The paper deals with instrumentation and control (I&C) of safety control systems (ESFAS) and normal operation control systems (NOCS) for NPP units. The research contains: general information on I&C of ESFAS and I&C of NOCS; description of design solutions for ESFAS, NOCS and principles of their implementation in I&C versions, description of basic components for design of I&C of ESFAS and I&C of NOCS. Distinctive features of ESFAS and NOCS I&Cs are the following: possibility to design systems with different number of channels in accordance with the design requirements; higher reliability due to redundant structures, including redundancy of analog-digital units and control drive units; minimization of cabling due to optical interface of data transmission using digital devices for remote control, indication and alarm in MCR (ECR); possibility of single redundant channel maintenance of I&Cs without losing operability; continuous monitoring of equipment of I&Cs, including diagnosing of input discrete signal channels and detection of hidden faults “on demand”.
Analysis of Conditions and Mechanisms for Generation of Explosive Mixtures at an Early Stage of Chornobyl Accident
Authors: Azarov S. , Sydorenko V. , Ievlanov V. , Havryliuk M.
Published: February 2019

The paper presents the scenario developed for an early stage of the accident progression to assess impact of highly explosive hydrogen on RBMK-1000 design. It was found out that the ratio between the speed of local generation of gaseous hydrogen and the speed of hydrogen spreading in the vapor-gas medium of the core is the determining factor for the occurrence of conditions of explosive vapor-air mixture in the core.

Obtained data can be used in further studies to model the formation of explosive mixtures in the environment, the amount of air and water vapor in the analysis of explosive vapor-air mixture. Practical calculations make it possible to assess fracture energy and predict the impact on structures.
Dynamics and directions for development of SSTC NRS international activity
Authors: Yesypenko Yu. , Pecherytsia O. , Shevchenko I.
Published: February 2019

The paper presents an overview of the key constituents of SSTC NRS international activity as of early 2017 and provides a number of examples. A tendency to further expansion of international activity is demonstrated. Areas and targets for further development and improvement of SSTC NRS international activity are identified.
Evaporation and Condensation Devices for Passive Heat Removal Systems in Nuclear Power Engineering
Authors: Gershuni A. , Pismennyi E. , Nishchik A.
Published: February 2019

The paper justifies advantages of evaporation and condensation heat transfer devices as perspective means of passive heat removal and thermal shielding in nuclear power engineering. The main thermophysical factors that limit heat transfer capacity of evaporation and condensation systems have been examined in the research. The results of experimental studies of heat engineering properties of elongated (8-m) vertically oriented evaporation and condensation devices (two-phase thermosyphons), which showed a high enough heat transfer capacity, as well as stability and reliability both in steady state and in start-up modes, are provided. The paper presents the examples of schematic designs of evaporation and condensation systems for passive heat removal and thermal shielding in application to nuclear power equipment.
Application of Methods for Analyzing Noises in VVER Diagnostic Systems
Authors: Borysenko V. , Budik D. , Horanchuk V.
Published: February 2019

The paper provides some research results obtained from the application of the diagnostic systems based on noise analysis methods and presents the history of implementing of noise diagnostic systems starting from the first VVER up to the present time. The research considered physical peculiarities of defining vibration parameters of reactor internals and fuel assemblies, as well as other parameters important to safe VVER operation. The paper presents the spectrum of the noise component of neutron detectors located in the core and outside the reactor pressure vessel. The main attention is paid to the capability of the comprehensive system to present diagnostics of such tasks, as the definition of coolant rate through the core and temperature coefficient of reactivity.
Vulnerability Analysis of Pipelines and Equipment of the Existing NPP Power Units with VVER-1000 under Vibrations Caused by the Aircraft Crash
Authors: Shamis L. , Matchenko T. , Veriuzhska T.
Published: February 2019

Low-frequency dynamic loads from earthquakes were taken into account in the design of the equipment and pipelines of the existing nuclear power plants. Therefore, in the case of an aircraft crash impact on a nuclear reactor containment, exciting intense high-frequency vibrations of the building, the reliability of the nuclear power plant cannot be guaranteed without the failure risk assessment of objects that are involved in the safe shutdown.

The paper suggests a method of the failure risk assessment using the concept of the ultimate resistance of pipelines and equipment of nuclear power plants to vibrations typical for the “aircraft crash” emergency design situation. The ultimate resistance is defined by the value of the load impulse, the application of which results in the probability of failure of the considered pipeline or equipment of 0.01 taking into account that it performs functions to provide 0.50 safety.
Evaluating Approaches to Estimating Endurance and Cyclic Cracking Resistance of Metal Structure Components
Authors: Matchenko T. , Matchenko P. , Shugaylo A. , Lyashenko L. , Panchenko A.
Published: February 2019

This paper considers issues on the life definition of category A structures for the buildings of CC3 class of consequences (liability) that may have defects at the beginning of operation or damages accumulated in the process of operation. The calculations to check resistance to cyclic loads shall be made for the stated structures at the design stage. The research includes analysis of requirements of Ukrainian and international regulatory documents for the calculation of structure components for quasistatic, low-cyclic fatigue and cyclic cracking resistance.
Comparative Analysis of Calculation Possibilities of MACCS and RODOS Computer Codes for Emergency Response and Analysis of Radiation Consequences of Severe Accidents at NPPs
Authors: Bogorad V. , Lytvynska T. , Bielov Ia.
Published: February 2019

The paper presents a brief description of the Real-time On-line Decision Support System (RODOS) and MELCOR Accident Consequence Code System (MACCS) and evaluates the application of these codes for assessment of radiation impact on the public and environment in case of a severe accident at NPP in real time mode. The experts performed comparative analysis of results obtained from calculations using RODOS, WinMACCS and HotSpot codes. In the framework of the research, the chosen comparative criteria were assessed: total effective dose, thyroid equivalent dose, skin equivalent dose, I-131 and Cs-137 ground concentration at different distances up to 50 kilometers from the source of release.
Geological Disposal of Radioactive Waste in Ukraine: History, Current State, Prospects
Authors: Shestopalov V. , Shybetskyi Iu.
Published: February 2019

The purpose of this paper is to analyze the state of geological repository development in Ukraine for the disposal of high-level waste and, possibly, of spent nuclear fuel. The data on state policy, activities and plans for disposal of radioactive waste, as well as on the results of scientific research aimed at the development of a geological repository are summarized. These data include siting, development of geological disposal concepts and safety assessment of selected concepts. Based on the analysis of the listed data, the main problems and further actions are identified.
Main Results of Assessing Integrity of RNPP-3 Steam Generator Heat Exchange Tubes in Accident Management
Authors: Shuhailo Ol-i. , Mustafin M. , Shuhailo Ol-r. , Ryzhov D. , Zhabin O.
Published: February 2019

Tubes integrity evaluation under accident conditions considering drain of SG and current technical state of steam exchange tubes is an important question regarding SG long-term operation and improvement of accident management strategy. The main investigation results prepared for heat exchange surface of RNPP-3 steam generator are presented in this research aimed at assessing integrity of heat exchange tubes under accident conditions, which lead to full or partial drain of heat exchange surface, in particular during station blackout.
Regulatory Nuclear and Radiation Safety Requirements for NPP Power Supply Systems
Authors: Levakin V. , Yefimova K. , Polyvoda S. , Iokst V.
Published: February 2019

The paper presents review of the requirements from the new regulation NP 306.2.205-2016 “Requirements for Power Supply Systems Important to Safety of Nuclear Power Plants” and recommendations of IAEA and WENRA for the construction of electrical systems important to safety of nuclear power plants. The research is focused on main differences of NP 306.2.205-2016 from standards that applied to NPP emergency power supply systems (PNAE G-9-026-90, PNAE G-9-027- 91) and which were cancelled in 2016.
On Shelter Transformation into Environmentally Safe System
Authors: Korchahin P. , Olkhovyk Yu.
Published: February 2019

The paper presents key issues requiring conceptual solution in a new updated strategy of Shelter transformation into an environmentally safe system before the beginning of activities on the retrieval of radioactive waste, in particular fuel-containing materials, after the commissioning of the New Safe Confinement.
Fission Ionization Chamber as Reference Source in Neutron Flux Analysis
Authors: Kuchmagra O. , Maznii I. , Odynokin H. , Sadovnikov A. , Skorbun A. , Stadnik S.
Published: February 2019

The paper considers the statistics of intervals between neutron registration by the detecting system based on fission ionization chamber KHT31-1, statistics of intervals between noise signal impulses in absence of neutrons and possibility to distinguish neutron flows from different sources. It is shown that spurious noise signal from alpha decay of 234U in a radiator of the ionization chamber KHT31-1 can be used as a reference signal in measuring neutron fluxes from different sources. The analysis of long-term continuous sets of measurements is taken as a basis of mathematical treatment.
Analysis of Terminology Used to Categorize Power Uprates of Nuclear Power Plants
Authors: Malynovska Yu. , Yesypenko Yu. , Vlasenko K. , Kovalchuk V. , Bodrova I. , Ved O.
Published: February 2019

Terms used for categorization of power uprates of nuclear power plants (NPPs) are analyzed in the paper. The power uprate program adopted in Ukraine is briefly described to emphasize importance of this area and need to use the appropriate terms. The categories of power uprates adopted by the U.S. NRC and applied by the IAEA are described. They include measurement uncertainty recapture, stretch, and extended power uprates. Translation of these terms into the Ukrainian language based on the analysis is proposed.
Mathematical Models for Investigation of WWER-1000/320 Transients
Authors: Nikulina E. , Severin V. , Lukinova D.
Published: February 2019

The paper presents mathematical models of the reactor WWER-1000/320, which are designed to investigate non-stationary operating modes of the reactor. The models in relative state variables include a point model of neutron kinetics with six groups of delayed neutrons and models of thermal processes, gradual heat generation, change in xenon concentration. The effects of reactivity on the movement of control rods and changes in reactor power, the effects of reactivity on changes in fuel and coolant temperatures, effect of change in the concentration of xenon are taken into account. The values of the constant parameters of the models are given for the start of stationary fuel loading.
Operational personnel decision-making supportautomatic system at nuclear power plant generating unitsby criterion of technical economic efficiency with dueconsideration of reliability factors
Authors: Yefimov A. , Kukhtin D. , Potanina T. , Harkusha T. , Kavertsev V.
Published: February 2019

New methods and approaches to development of nuclear power plant unit imitation models development. An imitation model is proposed for nuclear power plant unit developed on the basis of oriented graph applied to unit flow diagram description logic-numerical operators for calculation of parameters and characteristics determining its operation efficiency, reliability and safety. Automatic system is described developed on the basis of imitation model for decision-making support, applied to analysis of VVER nuclear power plant unit operation efficiency with due consideration of equipment operation reliability and safety indices.
Development of the matrix material selection algorithm for immobilization of transurane elements using the modified method of analysis of hierarchies
Authors: Skiter E.
Published: February 2019

The method of selecting the matrix material and the matrix synthesis method for immobilizing radioactive waste containing transuranium elements was developed using a system approach. A decomposition of the task of selecting and evaluating the selection parameters at different levels of the hierarchy has been carried out. An algorithm for solving the choice problem is proposed on the basis of the modified hierarchy analysis method. It is shown that the use of this algorithm in the selection of the matrix material makes it possible to take into account its radiation-chemical, physico-mechanical properties and technological parameters of the matrix synthesis methods, which makes it possible to make a motivated choice of the matrix optimal for immobilization of radioactive waste containing transuranium elements.
Perspective technology of recycling of radioactive contaminated metal based on its melting
Authors: Balakin V. , Mashinistov V. , Koveria A.
Published: February 2019

Melting of the radioactively contaminated metal converts it as a source of ionizing radiation from a surface distribution of radionuclides into the source with their volume distribution. From the surface of the melted metal gamma radiation of a part of radionuclides is emitted, which are in its scope. Alpha and beta radiation are absorbed completely in the metal.

To obtain a radiation-safe metal it is necessary that the amount of gamma-emitting radionuclides, which are loaded into the furnace together with the charge, did not exceed the established allowable level.

The radiation safety criterion of the melted metal is the maximum value of the gamma radiation power from its surface, the established limit of the individual annual effective radiation dose is not exceeded.

There is a need for experimental verification of theoretical results was obtained. The use of this technology will allow the return to industrial production of large amounts of accumulated radioactively contaminated metal and creates conditions for the prevention of environmental violations.
Assessment of the state of physical protection of nuclear facilities as a basis for the continued maintenance of the nuclear safety regime
Authors: Kuzmiak І. , Vagin G. , Kravtsov V.
Published: February 2019

The objective of this paper is examination of procedure of evaluation of status of physical protection systems of nuclear facilities, its normative regulation, interface with measures of nuclear and radiation safety evaluation and influence on integral status of nuclear security in Ukraine. For comparison was provided the short analysis of representation of physical protection requirements in regulatory acts for safety evaluation of nuclear facilities and in IAEA documents. The review of up-to-date status of legislation framework of physical protection, which implements the requirements on procedure of establishment and functioning of physical protection system and its elements and application of these requirements as basic criteria for evaluation of physical protection system is provided. Basing on results of review the possible ways of activation and enhancement of efficiency of evaluation of status of physical protection systems of nuclear facilities in Ukraine are determined. Particularly on of such ways is development of document containing the requirements for yearly reports on evaluation of status of physical protection system as well as for materials submitted with safety reports correspondingly to stages of life-cycles of nuclear facility.
The Main Results of Ageing Management State Analysis of Ukrainian NPPs
Authors: Shugailo A. , Plachkov G. , Grebenyuk Yu. , Shevchenko I. , Dybach О. , Zeleny O. , Moskalyshyn R.
Published: February 2019

The issues of ageing management (AM) are regarded as ones of the most important factors for safety ensurance of nuclear installations at the design and longterm operation stages. For Ukrainian NPPs units, the design lifetime (30 years) has either expired, or is at the ending stage. The Energy Strategy of Ukraine until 2035 “Safety, Energy Efficiency, Competitiveness” underlines the Long Term Operation (LTO) based on periodic safety review as one of the high priority areas of nuclear energy development. Thus, the analysis of ageing management issue is paid respective attention in Ukraine and abroad. Ageing management became a subject of first thematic peer review organized by European Commission based on Western European Nuclear Regulatory Authorities (WENRA) proposal. European Union countries took place in this peer review and Ukraine has joined this process as well. Based on the results of topical peer review each country has developed a National report on ageing management. This article is dedicated to main analysis results of ageing management issues at Ukrainian NPPs covering the components such as reactor vessel, containment, electric cables and embedded piping.Based on the results of independent verifications carried out by Western experts in the framework of international projects, the level of Ukrainian existing regulatory framework is in compliance with the level of the IAEA and WENRA documents and safety recommendations in the part of ageing management requirements. In addition, ageing management has a system basis. The areas of further activities on improvement of the regulatory framework taking into account the best practices and and experience, development of regulatory documents for research nuclear reactors, improvement of activities on assessment of the technical state and lifetime extension of reactor vessel along with the extension of the representative data based on the results of surveillanve specimens testing, conducting international peer reviews with the participation of the IAEA SALTO mission have been defined.
Criminal Liability for Illicit Trafficking of Radioactive Materials
Authors: Taran O. V. , Sandul O. G.
Published: February 2019

The nuclear energy use progressively becomes part of the life of every modern person, who more and more faces radioactive materials in medical institutions, in industry. Half of all electricity generated in Ukraine is generated by nuclear power plants. The peculiarities of the nuclear energy use generate appropriate rules for people dealing with radioactive materials. The article analyzes the standards of the Criminal Code of Ukraine, which provides for liability for acts related to the illegal handling of radioactive materials, for violation of the nuclear and radiation safety rules, violation of radiation safety requirements, the threat of theft of radioactive materials, the illicit manufacturing of a nuclear explosive device, abduction or capture of radioactive materials, attack on radioactive materials transportation means. The grounds and peculiarities for bringing to criminal liability have been reviewed, the range of persons who can be prosecuted has been defined. Conditions and grounds for exemption from criminal liability in the absence of a person's criminal intent to use radioactive material are considered. It has been demonstrated that the Criminal Code of Ukraine, by prohibiting certain actions on the illegal radioactive materials handling, ensures protection of the most important social relations and social benefits.
Study of the impact of NPP rated thermal power uprate on process behavior at different transient conditions
Authors: Nikulenkov A. G. , Samoilenko D. V. , Nikulenkova T. V.
Published: February 2019

Today, objective preconditions have been formed to find the ways on how to increase cost-effectiveness of NPPs operation, while providing the required safety level. One of such ways to increase thermal nominal power of power unit. The paper provides for the results of reactor behavior analysis at increased thermal power above nominal received using a one-dimensional system computer code RELAP5/MOD3.2 and relevant model of VVER-1000 (V-320) power unit. Calculation analyses are performed for quasi-static reactor operating conditions and transients using realistic approach in terms of initial performance parameters of reactor installation. In researches, representative initial events for transients have been selected according to the principle described further. For an abnormal operation, an event has been selected based on its high frequency and consequences, which require decreasing reactor power down to 50 % of nominal thermal power. For emergency conditions an event has been selected which is caused by external extreme impacts typical for Ukrainian NPP sites resulting in the worst consequences. Thus, the transients are represented by events associated with failure of a single turbine-driven feed water pump and total station blackout unit. To analyze emergency conditions caused by long-term blackout, they were additionally accompanied by a leakage through reactor coolant pump seals. Given that increase of steam flow in a turbine at increased thermal power above nominal requires additional studies on residual service life assessment of its critical components, a 3-D model of high-pressure rotor of a full speed turbine is proposed for further studies. Based on the calculations a comparative analysis of major parameters of the reactor at rated and increased thermal power is performed with assessment of significant factors to be considered in further studies on increase of installed thermal output of NPP unit.
Experimental Research of Valve Tightness at Different Closure Forces
Authors: Koroliov A. V. , Pavlyshyn P. Y. , Bandurko I. V.
Published: February 2019

Power valves are installed on almost all the pipelines of nuclear power plants performing the functions of regulation and shutting off the flow, so its failure often leads to emergencies. A particularly large number of failures is observed in motor-operated valves. Incorrect setting of the limiting clutch leads either to incomplete closure of the valve or to rod failure. Therefore, the valves are equipment of a nuclear power plant, which often falls into repair shops. Failures leading to an increase of valve leakage are especially dangerous for nuclear power plants. In this case, leakage of high-pressure valves leads to erosion of the sealing surfaces, which only increases the leakage. Thus, it is very important to determine the optimum rotational value when the valve is closed. The lack of conditions for closure force in the standards for valve leakage complicates the issue.

A bench that allows working in the air with a pressure up to 3.5 MPa was developed on valve rod to study dependence of valve leakage on the rotational moment. Four independent parameters were measured: air pressure in front of the valve under study, closure force of the valve, volume of air loss through the valve and leakage time. A standard stop valve with a nominal diameter of 15 mm and a nominal pressure of 64 atm was used for the study.

The determined dependence of the leakage on torque value allows recommending a gentler mode of valve closure without significantly reducing its tightness. As a result of experimental data processing, a criterial equation is obtained linking a leakage rate, pressure drop on the valve and a rotational moment value. The received criterial equation will allow defining the compromise between valve closure force and permissible leak level according to regulatory requirements. The analysis of the “leakage/rotational moment” diagram showed the possibility to reveal the damaged valves. This possibility may be used during the incoming inspection of the valves supplied to NPP, which should significantly improve the reliability of their operation.
The Issue Of Linear No-Threshold Hypothesis
Authors: Nosovskyi A. V.
Published: February 2019

Some issues concerning the effect of ionizing radiation on the human body and methodological approaches to the development of radiation safety standards are considered. It is shown that the use of the linear no-threshold hypothesis (LNT hypothesis) in up-to-date radiation safety standards is inconsistent with experimental and epidemiological dose-response data, introduces essential excessive conservatism in the safety assessment process and causes additional problems concerning nuclear power engineering development.

Due to the absence of convincing proofs for the existence of the dose threshold* nowadays, it is assumed that any ionizing radiation can lead to a certain risk of developing harmful effects and, therefore, the linear non-threshold dependence between the dose and the probability of the harmful effect is recommended. However, everyone understands that the use of the LNT hypothesis significantly overestimates the real danger. At the same time, the LNT hypothesis aggravates the existing high public fear of nuclear power, and the nuclear power industry pays extraordinary expenses to comply with radiation protection standards based on the LNT hypothesis. In order to comply with rules and regulations based on the LNT hypothesis, the nuclear energy industry invests financial resources in the creation of additional safety barriers for nuclear facilities, as well as new security and control systems. One of the reasons for increasing the cost for construction of a nuclear power plant is the increased design cost caused by enhanced safety requirements that are based on the LNT hypothesis.

The traditional engineering approach to ensure the safety of nuclear facilities is based on the increase in the number of protective systems and devices that reduce the probability of severe accidents and reduce the radiation hazard of their consequences. Implementation of this approach in practice leads to a complication and a rise in the price of a nuclear facility. Obviously, it is possible to substantially enhance the safety level of nuclear facilities by creating new and new safety barriers around them, but sooner or later the nuclear energy production will become uncompetitive compared to the generation of other kinds of energy.

It is concluded that up-to-date knowledge gives all the necessary grounds for eliminating the use of the linear no-threshold hypothesis and for revising the existing radiation safety standards of Ukraine for some isolated technological operations related to radiation hazardous activities. Such technological operations include activities related to the mitigation of radiation accident consequences, retrieval of nuclear materials and other activities related to the Shelter’s transformation into an environmentally safe system.
On the Nuclear Decision-Making Theory
Authors: Sandul G. O. , Sandul O. G. , Bulgakov A. O.
Published: February 2019

The study is devoted to the decision-making theory, its philosophical foundations and certain algorithms of practical activities. The paper is focused on activities in the field of nuclear industry.

The functioning of a technologically complex and large enterprise, for example, a nuclear power plant, is impossible without a complex management system, and the decision-making process is one of its elements. This paper is the primary description of the topic and its goal is to formulate approaches to several questions: why do we need a decision-making theory in general, how do we evaluate the correctness of an already made decision.

The significance of mathematical calculations in decision-making theory is described. The paper defines the basic terms that are used or will be used in the future, such as: methodology, technology, process, risk, human factor. The theoretical (philosophical) foundations that formed the basis of the decision-making doctrine are described, an attempt is made to answer the question why it is needed and by whom this theory is used and for what purpose. The connection between decision-making with the human factor is formulated. The distinction between the concepts of “decision” (as already existing) and “making decision” (as a complex process, a system of management actions, forecasting options and choosing between them) is described.

Certain procedures are presented in the implementation of the decisionmaking process in order to show possible approaches, stages and decisionmaking techniques, as well as the readiness to implement a specific solution. The dependence (efficiency) of the management organization on the decisions made and their implementation is indicated. Besides, the paper sets forth the logic of making the “right” decisions based on “information”.

The authors conclude about the importance of applying the decisionmaking theory during the safety analysis and predicting the likely extreme situations at nuclear power facilities and the need to continuously improve the management structures.
Pengaruh Model Pembelajaran Kooperatif Tipe Think-Pairs-Share Dalam Pembelajaran Matematika Terhadap Kemampuan Pemahaman Konsep Matematis dan Pengembangan Karakter Siswa SMA Kota Sungai Penuh
Authors: Sari Maila , Habibi Mhmd , Putri Rahmi
Published: February 2019

Guru matematika dituntut tidak hanya dapat menstransfer ilmu pengetahuan saja kepada peserta didik, namun juga dapat membentuk dan mengembangkan karakter siswa dalam proses pembelajaran matematika. Untuk dapat menumbuhkan dan mengembangkan karakter siswa dibutuhkan suatu model pembelajaran yang dapat memunculkan indikator pembentukan karakter dalam proses pembelajaran. Model pembelajaran yang dapat memunculkan indikator pengembangan karakter adalah model pembelajaran Think - Pairs – Share (TPS). Penelitian ini bertujuan untuk mengetahui 1) kemampuan pemahaman konsep siswa yang menggunakan model pembelajaran TPS dan kemampuan pemahaman konsep siswa yang tidak menggunakan model pembelajaran TPS, 2) karakter jujur, tanggung jawab, dan disiplin siswa yang menggunakan model pembelajaran  TPS dan karakter jujur, tanggung jawab dan disiplin siswa yang tidak menggunakan model pembelajaran TPS. Hasil analisis data menunjukkan bahwa: 1) kemampuan pemahaman konsep siswa yang menggunakan model pembelajaran TPS lebih baik dibandingkan dengan kemampuan pemahaman konsep siswa yang tidak menggunakan model pembelajaran TPS, 2) karakter jujur, tanggung jawab, dan disiplin siswa yang menggunakan model pembelajaran  TPS TPS lebih baik dibandingkan dengan karakter jujur, tanggung jawab dan disiplin siswa yang tidak menggunakan model pembelajaran TPS.
EDUPARENT BAGI ORANG TUA SISWA TK DHARMA WANITA SULUK DLOPO KABUPATEN MADIUN
Authors: Betty Yulia Wulansari M. Fadlillah,
Published: February 2019

Tujuan utama kegiatan pengabdian kepada masyarakat ini adalah untuk memberikan pendidikan keorangtuaan kepada orang tua siswa di TK Dharma Wanita Suluk Dlopo Kabupaten Madiun. Metode pengabdian dilakukan dengan mengadakan sosialisasi melalu seminar eduparent (pendidikan keorangtuaan). Tema eduparent dalam kegiatan pengabdian ini yaitu melatih kemandirian anak usia dini. Sasaran pengabdian ini adalah orang tua siswa di TK Dharma Wanita Suluk Dlopo Kabupaten Madiun. Hasil kegiatan pengabdian ini adalah orang tua siswa mampu mengetahui dan memahami perannya dalam mengasuh dan memperlakukan anak, khususnya dalam melatih kemandirian anak usia dini. Orang tua siswa sangat antusias mengikuti kegiata dari awal sampai selesai, sehingga mereka mendapatkan wawasan dalam melatih kemandirian anak usia dini sesuai dengan tahap perkembangannya.
ANALISIS TINGKAT PENGGUNAAN ICT GURU TK KECAMATAN GROGOL KABUPATEN SUKOHARJO
Authors: Irmade Oka
Published: February 2019

Penelitian ini bertujuan untuk mengetahui Tingkat penggunaan ICT guru TK di Kecamatan Grogol Kabupaten Sukoharjo yang dibagi berdasarkan kriteria ketersediaan fasilitas atau infrastruktur ICT, pemanfaatan ICT, dampak ICT pada proses pembelajaran TK. Penelitian ini merupakan studi deskriptif. Jenis penelitian yang digunakan adalah deskriptif kuantitatif. Subjek penelitian ini adalah guru TK di Kecamatan Grogol Kabupaten Sukoharjo sebagai penelitian yang berjumlah 154 guru dari 47 sekolah yang kemudian dilakukan penarikan sampel dengan teknik simple random sampling menjadi 110 guru. Data diperoleh peneliti menggunakan metode survei dan mengumpulkan data melalui distribusi kuesioner. Hasil yang didapat dari penelitian ini adalah ketersediaan fasilitas atau infrastruktur ICT TK di Kecamatan Grogol Sukoharjo cukup memadai, ini bisa terlihat dari 47 sekolah ada 33 sekolahan yang mempunyai fasilitas lengkap meskipun 14 sekolah belum mempunyai fasilitas internet. Guru lebih banyak menggunakan komputer untuk kepentingan atau kebutuhan di sekolah saja. Penggunaan internet cukup tinggi, minimal 10 jam perminggu. Dari seluruh guru mengatakan perkembangan ICT berdampak positif. ICT dapat mempermudah mencari bahan ajar, guru tidak ketinggalan informasi dan perkembangan IT, memudahkan guru dalam mengajarkan ilmu pada anak, kegiatan belajar mengajar jadi menyenangkan, menambah minat belajar, memudahkan proses belajar mengajar dan mencari media
MENINGKATKAN KEMAMPUAN SAINS MELALUI PERMAINAN WARNA DENGAN MENGGUNAKAN CAT AIR PADA ANAK KELOMPOK B TK NEGERI PEMBINA KABUPATEN TEMANGGUNG
Authors: Riastuti Rini
Published: February 2019

Tujuan dari penelitian ini adalah 1) untuk mengetahui pelaksanaan pembelajaran permainan warna dengan menggunakan cat air dalam meningkatkan kemampuan sains anak, 2) untuk mengetahui peningkatan kemampuan sains pada anak setelah kegiatan permainan warna dengan menggunakan cat air di Kelompok B TK Negeri Pembina Kabupaten Temanggung Semester I Tahun Pelajaran 2017/2018. Berdasarkan hasil penelitian dan pembahasan, maka dapat disimpulkan bahwa kemampuan sains anak Kelompok B TK Negeri Pembina Kabupaten Temanggung dari kondisi awal sampai dengan dilaksanakannya perbaikan pembelajaran sampai dengan Siklus II telah mengalami peningkatan yang sangat signifikan.  Pada kondisi awal, anak yang mampu menunjukkan kemampuan sainsnya hanya 3 anak (20%) dari 15 anak. Berdasarkan perbaikan pembelajaran yang diperoleh pada Siklus I, maka dapat dilihat hasil penelitian bahwa anak yang mampu melaksanakan permainan  warna dengan kriteria berkembang sesuai harapan 7 anak (46,7%), mulai berkembang 2 anak (13,3%), dan belum berkembang 6 anak (40%). Setelah diadakan perbaikan pembelajaran pada Siklus II anak yang dianggap mampu dengan kriteria berkembang sesuai harapan 13 anak (86,8%), mulai berkembang 1 anak (6,6%), belum berkembang 1 anak (6,6%) dan telah mencapai standar ketuntasan belajar yang telah ditetapkan dengan kriteria anak tertarik dalam kegiatan bermain warna, anak mampu mencampur warna dengan baik, dan anak mampu menjawab pertanyaan dari peneliti.
Lysozyme transport to the brain by liposomes
Authors: Nordling-David Mirjam M , Rachamin Elior , Grad Etty , Golomb Gershon
Published: February 2019

Delivery of drugs into the brain is limited due to poor penetrability of many drugs via the blood-brain barrier. Previous studies have shown that the brain is kept under close surveillance by the immune system, implying that circulating phagocytic cells, such as neutrophils and monocytes, are crossing the blood-brain barrier. We hypothesized that charged liposomes could be transported to the brain following their phagocytosis by circulating monocytes. In this work, we investigated the capacity of circulating monocytes to be exploited as a drug delivery system following IV administration of nano-sized, positively fluorescently labeled liposomes containing the protein lysozyme. Negatively charged fluorescently labeled liposomes were used for comparison. By using a modified thin-film hydration technique, the desired properties of the liposomal formulations were achieved including size, polydispersity index, high drug concentration, and stability. In vitro results showed a significant time-dependent uptake of positively charged liposomes by RAW264.7 cells. In vivo results revealed that circulating white blood cells (mainly monocytes) contained high levels of fluorescently labeled liposomes. Screening of brain sections using confocal microscopy uncovered that a substantial amount of fluorescently labeled liposomes, in contrast to the fluorescent markers in solution, was transported into the brain. In addition, anti-CD68 immunofluorescent staining of brain sections demonstrated co-localization of positively charged liposomes and macrophages in different brain sections. Furthermore, significantly higher levels of lysozyme were detected in brain lysates from rats treated with positively charged liposomes compared to rats treated with lysozyme solution. Taken together this confirms our hypothesis that the designed liposomes were transported to the brain following their phagocytosis by circulating monocytes.
A coming era of precision diagnostics based on nano-assisted mass spectrometry
Authors: Li Rongxin , Gurav Deepanjali Dattatray , Wan JingJing , Qian Kun
Published: February 2019

Precision diagnostics relies on omic analysis by mass spectrometry to overcome the limitation in accuracy by an individual biomarker, due to the complex nature of diseases. Recent development in nanotechnology markedly enhanced sample treatment and detection efficiency of this method. Herein, we foresee a coming era of precision diagnostics based on nano-assisted mass spectrometry. Some important progress in the field includes detection of (1) nucleic acids for genetic analysis; (2) proteins/peptides for proteomic analysis; and (3) small molecules for metabolic analysis. We anticipate that this review will be a reminder for both young and experienced researchers about the future of diagnostics and call for attention worldwide.
Student Experience Conducting Transactions Buy and Sell Salam (orders) On-Line
Authors: Azulaidin Azulaidin
Published: February 2019

the aim of this paper to give solution to muslim in buying-sell product On-Line to avoid Gharar and Riba in Muamalah system. There are two kinds of buying and selling in practice, namely buying and selling directly and buying and selling indirectly. Direct buying and selling, for example: buying and selling in traditional markets and minimarkets / supermarkets where the buyer can check or choose the item to be bought directly. While, indirect buying and selling can be done by buying and selling Salam (orders). To collecting the data, the researcher uses interviews method.
Student Experience Conducting Transactions Buy and Sell Salam (orders) On-Line
Authors: Azulaidin Azulaidin
Published: February 2019

The aim of this paper to give solution to muslim in buying-sell product On-Line to avoid Gharar and Riba in Muamalah system. There are two kinds of buying and selling in practice, namely buying and selling directly and buying and selling indirectly. Direct buying and selling, for example: buying and selling in traditional markets and minimarkets / supermarkets where the buyer can check or choose the item to be bought directly. While, indirect buying and selling can be done by buying and selling Salam (orders). To collecting the data, the researcher uses interviews method.
The Creation of Campus Cafe in Getting Profit
Authors: Hayati Fitri
Published: February 2019

The culinary business recently becoming trend is blocked by people. Café is a vehicle for people to gather, play and work and so on. Attractive offers are always served at Cafés ranging from food and drinks with unique variations in accordance with the café theme itself. This cafe business has become a business attraction. This is because people are more comfortable in the café for more relaxed activities. Café is also a flexible place for everyone. In addition to its convenient location, the café also often offers Free WIFI. The aim of research is to find a successful method of running a café business with limited business capital. The research method is a qualitative method. The researcher examined the success tips used by the Campus Cafe on Selamat Ketaren Street No.1 and 2, Percut Sei Tuan, Medan City, North Sumatra 20371 with the name of the owner of Sultoni's brother. This cafe is just the grief of the owner, starting from unsold merchandise until employee changes. Not infrequently also the owner suffered a loss. But now this Campus Cafe has started to develop rapidly. Its existence has begun to compensate for the cafes around Jalan Selamet Ketaren, especially the Aceh Corner, which is always crowded with customers. It operates for approximately 3 years.