bluuebunny/crossref_metadata_2025 huggingface dataset:
Değişim çağında yeni nesil para: Kripto paraların avantaj ve dezavantajlarına yönelik inceleme
Authors: Arıcı Tuğkan , Kitapçı Hakan , Fidan Eray
Published: January 2022

Satoshi Nakamoto tarafından 2008 yılında kaleme alınan “A Peer-to-Peer Electronic Cash System” makale ile hayatımıza giriş yapan sanal para (kripto para) konusu son yıllarda hem yatırımcıların hem de hükümetlerin dikkatini çekmektedir. Dağıtılmış ağlar aracılığıyla merkezileşmeyi yok eden ve herhangi bir otoriteye bağlı kalmadan işlem yapabilmeyi sağlayan kripto paralar, geleneksel para sistemlerinde bulunan aracı gibi dezavantajlı oluşumları aradan kaldıran, maliyetleri düşüren, daha hızlı ve güvenilir ödeme yöntemleri olarak ortaya çıkmaktadır. Finans ve girişimcilik başta olmak üzere paranın kullanım alanı ve kullanım yöntemlerinde çeşitli yenilikler ve kolaylıklar sunan kripto paralar, beraberinde getirmiş olduğu avantaj ve dezavantajları nedeniyle günümüzde anlaşılmaya çalışılan en önemli konu başlığı olarak karşımıza çıkmaktadır. Özellikle son dönemde Çin’in kripto para borsasına işlem yasağı getirmesiyle beraber kripto paraların mevcut durumu, hükümetlerin kripto paralara bakış açılarının neler olacağı ve değişen dünya düzeninde kripto paraların nasıl bir yer tutacağı merak konusu olmaya başlamıştır. Bu çalışmanın amacı kripto paralar üzerine literatürde yer alan mevcut çalışmaların incelenmesi sonucunda kripto para teknolojisinin hem yatırımcılar ve hükümetler için sağlayacağı avantaj ve dezavantajlarının neler olduğunun belirlenmesi hem de gelecek araştırmalar için araştırmacılara yol gösterilmesi hedeflenmiştir.
Perilaku Konsumsi Garam Dan Gula Pada Mahasiswa Fakultas Kedokteran Universitas Tadulako Angkatan 2020
Authors: Tangkilisan Georgiana Patricia , Handayani Fitriah , Suarayasa Ketut , Fitriana Yuli
Published: January 2022

The objective of this research is to find out the knowledge, attitudes, and behavior of sugar and salt consumption among students at the medical faculty of Tadulako University in the 2020 batch. Methods: This research method is descriptive quantitative. The sample totaled 157 respondents selected through the total sampling technique. Results: A total of 156 respondents filled out the questionnaire. The results of the research are as follow: Students who have good knowledge about sugar and salt consumption on age 17 to 19 years of 66.4%, age 20 to 22 years of 68.2%. The characteristic of gender which has good knowledge about sugar and salt consumption is female of 71.3%, male of 50%. The characteristic of age which has a positive attitude about consuming sugar and salt is 17-19 years of 100%, 20-22 years of 95.5%. The female gender has a positive attitude about sugar and salt consumption of 99%, the male is 100%. Aged 17-19 years have positive behavior about consuming sugar and salt of 98.5%; age 20-22 years of 95%. The female gender has positive behavior regarding sugar and salt consumption of 97.5%; male of 100%. The top three foods frequently consumed by respondents were Siomay (16.4%), Indomie fried noodle (15.7%), and fried rice (10%). The top three drinks frequently consumed by the respondents are Pop-Ice (18.4%), Nutrisari Orange (16.9%), and Orange Juice (15.4%). Conclusion: There is good knowledge, positive attitudes and positive behavior about salt and sugar consumption in medical students at the medical faculty of Tadulako University in the 2020 batch.
A comparative study of antimicrobial effects of Clitoris ternatea and Anacardium occidentale leaf extracts against the selected microbes
Authors:   Department of Zoology, Anwarul Uloom College, Hyderabad, Telangana State, India, Ali Siddiqui Akhter , Ahmed Arif ,   School of Sciences (Zoology), Maulana Azad National Urdu University, Hyderabad, TS, India, Begum Rizwana
Published: January 2022

The aim of the present study was to investigate a comparative study of antimicrobial efficacy of Clitoris ternatea and Anacardium occidentale leaf extract against Staphylococcus aureus, Streptococcus pneumoniae, Mycobacterium tuberculosis and Bacillus subtilis (Gram-positive), and Pseudomonas aeruginosa, Klebsiella pneumonia, Proteus vulgaris, and Salmonella typhi (Gram-negative) microbial strains. Ethanol extracts of both the leaf were evaluated against the experimental microbial strains using the well diffusion and agar disc diffusion methods. The present investigation showed that some microbial strains were more sensitive to Clitoris ternatea as compared to Anacardium occidentale and vice versa. But on the whole the Clitoris ternatea was found to be more effective than Anacardium occidentale. It is concluded that both the extracts showed antimicrobial activity due to the presence of bioactive phytochemicals present in them.
Ichthyofaunal diversity and conservation status of Siddheshwar reservoir district Hingoli, Maharashtra, India
Authors:   Department of Zoology, Adarsh College, Hingoli-431513, (M.S.), India, S. Patode Priyanka , Salve B.S. ,   Department of Zoology, Adarsh College, Hingoli-431513, (M.S.), India, Pawar R.T. ,   Department of Zoology, Sunderrao Solanke Mahavidyalaya, Majalgaon, Dist. Beed, (MS), India
Published: January 2022

The study of ichthyofaunal diversity of Siddheshwar reservoir, district Hingoli, Maharashtra, was conducted over a two-year period from January 2015 to December 2016, and the reservoir shows occurrence of rich ichthyofaunal diversity, with a total of 40 fish species belonging to 29 genera, 15 families, and 9 orders in Siddheshwar reservoir. The order Cypriniformes dominated with 18 species, followed by the orders Siluriformes with 8, Channiformes with 4, Preciformes with 3, Clupeiformes and Mastcembeliformes with 2, and the rest of the orders Angulliformes, Beloniformes, and Mugiliformes with a single species. Because of the abundance of food materials, most of the significant fishes may be found in this reservoir. Primary productivity occurs in the form of primary producers (Phytoplanktons and Zooplanktons). According to the IUCN red list categories, 52.5 percent of the species are least concern, 20 percent are not evaluated, 10 percent are near threatened, 5.00 percent are data deficient, 5.00 percent are lower risk near threatened and vulnerable, and 2.5 percent are lower risk least concern. The study reveals that this freshwater body could be beneficial to regional fish variety conservation, particularly for indigenous and endangered fish species.
ESTIMATING THE CHANGE OF A MASS EXCHANGER PRODUCTIVITY ON ACCOUNT OF OXYGEN RESOURCE DECREASING
Authors: Askhadullin R , Legkikh A
Published: January 2022

The most important impurity in the heavy liquid metal coolant (HLMC) is dissolved oxygen. When the dissolved oxygen is entered into the coolant the oxide films is formatted on the surfaces of structural steels and equipment. The films provide the corrosion resistance of the surfaces against influence of the coolant. The state of the protective films during operation is largely determined by the oxygen regime, i. e. a concentration of dissolved oxygen in the coolant. So-called natural deoxidation of the coolant, which is spontaneous reduction of the dissolved oxygen content, is characteristic of hermetic non-isothermal circulation circuits with HLMC due to the thermodynamic features of "HLMC-impurity-structural steel" system. As a result, the oxygen concentration decrease and it can achieve the levels, in which corrosion and erosion processes start. To maintain the oxygen concentration on the level for ensuring of corrosion resistance of the steels the control the oxygen concentration and regulated feed of the coolant with dissolved oxygen is necessary. To control the oxygen concentration, the sensors of oxygen activity are used. The sensors are based on a solid oxide electrolyte and developed in the SSC RF - IPPE. The most perspective method to inject the dissolved oxygen into the coolant is solid phase method. It is based on dissolution of solid-phase lead oxide in the coolant flow. The technical realization of the solid-phase method of maintaining the oxygen concentration is carried out with the help of mass exchangers. At the stage of designing the mass exchanger, it is necessary to calculate the main technical parameters of its operation; one of this is oxygen productivity. During the operation of mass exchanger its productivity will change on account of oxygen resource decreasing. It is important for practice to estimate the change of the mass exchanger productivity and the resource of its operation. In the report our approach of estimating the change of mass exchanger productivity on account of oxygen resource decreasing is presented.
THE SOLUTION TO THE PROBLEM OF THE SPENT FUEL OF THERMAL REACTORS IN A TWO-COMPONENT SYSTEM OF ATOMIC ENERGY
Authors: Kagramanian V , Chebeskov A , Decusar V , Gurskaya O
Published: January 2022

To date, several conceptual models of the organization of a two-component nuclear power system have been proposed in the world. This report presents the schematic diagrams of these models, briefly describes their main tasks and prospects for their implementation with time. As a result, based on the preliminary analysis, a model of a two-component nuclear energy system with thermal and fast reactors operating in a single closed nuclear fuel cycle is proposed. Such a model, based on existing and demonstrated technologies of thermal and fast reactors, can solve the main problems of current nuclear power, consisting in the uncontrolled accumulation of SNF volumes of thermal reactors and the inefficient use of natural uranium.
THE FIRST IN THE WORLD REACTOR WITH LEAD-BISMUTH COOLANT (FACILITY 27/VT). HOW THAT STARTED
Authors: Toshinsky G
Published: January 2022

Development of reactor facilities (RF) with lead-bismuth coolant (LBC) was carried out in conditions of lack of necessary knowledge and experience. Moreover, there were fixed directive terms of work completion, which practically eliminated the opportunity for performance of related scientific and research works that was a reason of multiple failures at the stage of mastering of that technology. In the presented report the following issues are considered: the reasons for option of eutectic lead-bismuth alloy as coolant, principal scientific and technical problems solved in the process of mastering of LBC cooled RFs including the problem of coolant technology and corrosion resistance of steels, providing of radiation safety when realizing works related to release of polonium, providing of reliability of steam generators, incidents and accidents happened in the process of operating and ways for elimination of their reasons, experience of fuel unloading performance. On the whole, in the process of performing tests at Facility 27/VT the invaluable experience was obtained that made possible elimination of the reasons of happened accidents and provide reliable operation at RFs of serial nuclear submarines (NS) of Project 705 (705K). On the basis of critically analyzed operating experience, the civilian RF project, namely SVBR-100 that is meeting the Generation IV requirements is being developed.
COMPARISON OF HOMOGENEOUS AND HETEROGENEOUS USE OF ENERGY PLUTONIUM IN VVER
Authors: Tsibulskiy S
Published: January 2022

There are separate of fissile isotopes in a fuel rod in the fuel load admit the transition to a closed fuel circle in the nuclear power industry. For this solution to consider the formation of heterogeneous fuel pellet in which the fissile and raw isotope are separate and not mixed together. The raw material isotope is located in the peripheral zone. Fissile isotope, placed in the center of fuel pin holds 10% of the volume. There is row isotope in the periphery. All calculations for this research were made with UNK code. This code was complemented with a module, which allows calculating temperatures in pin cell. At present UNK allows solving of neutron-physical task of neutron transport, burn-up task (isotope composition evolution) and temperature calculation. Initial loading is plutonium, separated from spent fuel of the same cell of previous company. Irradiated plutonium of the central part is sent to either long term storage or final disposal. Energy plutonium location extracted from spent fuel of VVER in the central part of fuel pellet (heterogeneous pellet) decreases plutonium loading approximately 20 % in condition of the same company duration in comparison with UOX fuel. In case of heterogeneous location, there is depleted uranium in the periphery on the pellet. And after irradiation received plutonium isotope composition can be used repeatedly to form new loadings. This solution is qualitatively different from MOX case, which does not allow further using.
THERMAL PHYSICS OF ALKALINE LIQUID METAL COOLANTS. PART 1: THERMOHYDRAULICS AND SAFETY (RETROSPECTIVE-PERSPECTIVE VIEW)
Authors: Kuzina Ju , Sorokin A
Published: January 2022

As a result sixty years of experience in the development of alkaline liquid metals - sodium, eutectic alloys of sodium-potassium, lithium, cesium, the scientific bases of their application in nuclear power were created, the thermohydraulic parameters and highly efficient technological processes were substantiated, devices and systems were developed and implemented that ensured the successful operation of fundamentally new NPPs. The main areas of research were: thermal hydraulics, mechanisms of turbulent heat exchange, boiling and condensation of liquid metals, physical chemistry and liquid metal coolant technology, thermophysical properties of materials of the reactor, coolants, analysis and generalization of thermophysical data, bases of the experimental data, heat pipes, thermophysics of thermionic converters, high-temperature space nuclear power units and thermonuclear installations. The results investigations of hydrodynamics and heat transfer in channels of complex shape were studied, both under normal operating conditions and deformation of a fuel cell grid. The justified reduction of collector hydraulic irregularities in reactors, heat exchangers and steam generators. A channel-by-channel method of thermal-hydraulic calculation of fuel assemblies of the core of fast reactors for nominal and non-nominal operating regimes was developed. A theory of anisotropic porous body has been developed as applied to calculations of complex flows in reactors, heat exchangers and steam generator. Experimental investigations of the circulation and heat transfer in the reactor tank during forced circulation, in transitional and accident regimes with natural circulation showed a stratification and temperature pulsations in the upper mixing chamber and other regimes of the reactor installation. The boiling processes in a large volume, tubes and bundles of rods, the condensation of liquid metals, the occurrence of accident processes during sodium leaks in steam generators and sodium circuits have been experimentally investigated. The tasks of further research are formulated.
DEVELOPMENT AND TESTING OF FULL-SCALE MATHEMATICAL MODEL OF A TRANSPORT CONTAINER FOR RADIATION SAFETY EVALUATION BY THE MONTE-CARLO METHOD DURING CARTING SPENT FUEL OF VVER-1000 AND VVER-1200
Authors: Bikeev A , Daichenkova Yu , Kalugin M , Oleynik D , Shkarovskiy D
Published: January 2022

In recent years, new approaches have been developed to ensure radiation safety during carting spent nuclear fuel from nuclear power plants with VVER-1000 and VVER-1200 reactors, because the height of the fuel assembly and the initial enrichment of fuel have increased; operating modes of reactors have changed and average burnup in fuel assemblies has increased; new requirements about two safety barriers and prohibition on using liquid neutron protection has appeared. The new generation transport container is designed to cart 18 spent fuel assemblies of VVER-1000 and VVER 1200 reactors to long-term storage. The main objective of the work is development and testing of the full-scale mathematical model of the new generation transport container for analysis of radiation safety using the Monte Carlo method, as well as performing numerical studies on the selection of optimal non-analog modeling parameters. Using the simple iteration method, the optimal values of the splitting surfaces for the non-analog modeling method “weight window” were determined. The developed three-dimensional highly detailed model makes it possible to take into account the contribution to the equivalent dose rate from ionizing radiation sources in the top and bottom nozzles, reduce the number of conservative approximations, and, thus, increase the accuracy of radiation safety analysis. Increasing the accuracy of calculating the equivalent dose rate on the surface of the transport container may make it possible to cart spent fuel assemblies with a greater burnup.
RESEARCH OF HIGH-TEMPERATURE NUCLEAR ENERGY TECHNOLOGY FOR THE PRODUCTION OF HYDROGEN AND OTHER INNOVATIVE APPLICATIONS
Authors: Sorokin A , Gulevich A , Klinov D , Kuzina Yu , Kamaev A , Ivanov A , Alekseev V , Morozov A
Published: January 2022

The presented results of neutron-physical, thermophysical, and technological studies have shown that it is possible in principle to provide the required parameters of a high-temperature (900-950 °C) reactor installation with a 600 MW reactor (heat) with a sodium coolant for hydrogen production and other innovative applications based on one of thermochemical cycles or high temperature electrolysis with a high coefficient of thermal use of electricity. The relative small size, type of coolant, and the choice of fissile material and structural materials make it possible to create a reactor with intrinsic properties that provide enhanced nuclear and radiation safety. The possibilities of using heatresistant radiation-resistant structural materials and using the proposed technology of hightemperature sodium coolant at a high hydrogen concentration are discussed. The features of the behavior of a high-temperature complex multicomponent heterogeneous system ″sodium coolant - impurities - structural (technological) materials - protective gas″ are analyzed, which are associated with an exponential temperature dependence of constants characterizing heat and mass transfer processes (diffusion, permeability, solubility, absorption rate, equilibrium gas pressures, etc.). It has been shown that the technology system for high-temperature sodium coolant differs significantly from systems at modern nuclear power plants. With an increase in the intensity of hydrogen sources coming from the third circuit to the second, compared with BN-600 NPPs by two to three orders of magnitude, the condition for its implementation is to increase the hydrogen concentration in sodium by two to three orders of magnitude compared to modern nuclear power plants in combination with the removal of hydrogen from sodium by evacuation through membranes from vanadium or niobium.
INFORMATIVENESS OF MODELING PROMPT DOWNING OF CONTROL RODS IN SPACE-TIME CALCULATIONS OF FAST REACTORS
Authors: Zizin M
Published: January 2022

Based on the computational studies of the spatial neutron kinetics benchmarks, the advantages and disadvantages of modeling the control rods (CR) prompt downing in space-time calculations of fast reactors are formulated. Prompt downing of the CR is only useful when the benchmarks calculating. In space-time calculations, the reactivity was calculated using an inverted solution of the kinetic equation. The conclusions are made based on a comparative analysis of the simulation of prompt downing and gradual movement of the control rods in two benchmarks - BN600_IAEA_T and MET-1000_T. BN600_IAEA_T is a model of a BN-600 type reactor with a hybrid core, and MET-1000_T is a model of a medium-sized fast reactor with a metal fuel with a thermal capacity of 1000 MW (t). Simulation of prompt downing of control vrods is recommended for debugging algorithms and codes for solving the transport and spatial kinetics equations. Its advantages include a significant reduction in calculating times and, as a result, easing the most time-consuming stages of cross-validation of codes. The disadvantages are associated with the inability to find errors in the modeling of the gradual movement of the CR. It is shown that recalculating the concentrations of delayed neutron precursors when solving the transport equation in a pre-set number of mandatory external iterations significantly increases the accuracy of reactivity calculations. The quasi-prompt downing of the control rods is almost equivalent to their prompt or the reactivity and power calculations. The power reactor values calculated after the prompt downing of the control rods differ significantly from the power values calculated for the moments after the end of the CR downing when items are gradually downing at 1 m/s speed. As the rate of downing the CRs increases, the power values approach those calculated after an prompt downing r of the CRs.
FEATURES OF THE CORE OF PERSPECTIVE FAST REACTORS
Authors: Klinov D , Gulevich A , Eliseev V , Malysheva I , Buryevsky I
Published: January 2022

In the pre-Chernobyl period, the task of fast reactors was to provide fuel for the intensive development of nuclear energy with a deficit of natural uranium: short doubling time, high HF, high heat intensity, short campaign. After the Chernobyl accident, the main thing was to ensure safety, including in beyond design basis and postulated accidents. Modern fast sodium reactors must, on the one hand, satisfy the safety requirements in design and beyond design basis accidents (in accordance with the requirements of GEN-IV), and on the other, be competitive in comparison with water reactors and other energy sources. The article discusses the methods of transformation of the core of existing and planned Russian fast reactors to meet these requirements. The safety of these reactors in design and beyond design basis accidents is ensured by rejecting the upper end shield and replacing it with a sodium cavity, which allows reducing the NER and ensuring the input of negative reactivity when sodium boils. Such an core is implemented in BN-800 and the designed BN-1200. Improving the competitiveness (increasing the duration of the fuel campaign and KIUM) of the designed and existing reactors is ensured by switching to radiation-resistant clad steel EK164 (currently sold in BN-600, planned in BN-800) and the transition to the core with an axial layer of depleted uranium dioxide (planned for BN-800 and BN-1200). In BN-1200, due to the abandonment of a number of switchgear elements and optimization of the design, a one-and-a-half reduction in metal consumption is achieved. For fuel economy, a ″thick″ fuel rod with a diameter of 9.3 mm and a fuel campaign of 4 years have been adopted. This reduces the annual consumption of fuel rods and fuel assemblies by 2-2.5 times. Both events require modernization of the core. Each of these events allows you to increase the duration of the campaign by 25 %, and the implementation of both measures (transition to new steel and the introduction of a layer) will allow you to increase the campaign and reduce fuel consumption by more than 50 %. The introduction of the axial layer does not require core expansion, which gives additional fuel savings. But the axial layer should not be located in the central plane of the core, but with a shift of 3-5 cm downward. This will improve many characteristics of the core: increase fuel enrichment by a quarter and, as a result, proportionally reduce the neutron flux and radiation damage to the claddings of fuel elements; increase the fuel campaign to 5 years; to reduce the reactivity margin for burnout, without compromising the effectiveness of the control systems, to increase the micro-campaign to 1 year; to level the heat-release field in the vertical direction, to reduce the maximum heat intensity; to improve the course of beyond design basis accidents like ULOF. This method of reducing the rate of accumulation of a damaging dose is equally effective for both MOX and nitride fuels, which makes it possible to unify the core design.
COST ASSESSMENT OF DIFFERENT RADIOACTIVE WASTES OF REPROCESSED PRIMARY SODIUM FROM FAST REACTORS FOR FINAL BURIALE
Authors: Dolgikh V , Zabrodskaya S , Lebedeva O , Popov E , Smykov V
Published: January 2022

One of the main arisen problems during decommissioning of fast reactors is the reprocessing of radioactive primary sodium. After final shut down of fast reactor the reprocessing of sodium in the safe material for final burial demands the long and height-cost procedures because the primary sodium is the fire-explosive-danger metal and it has the appreciable radioactivity. The compare cost assessments for final burial of different radioactive wastes of reprocessed primary sodium from RR BR-10 and NPP BN-600 are accomplished in article. The assessments are performed for two possible reprocessing of primary sodium: by direct one-stage solid-phase oxidation and immobilization technology in solid mineral stone (SPO, IPPE, RR BR-10, Russian patent N 2200991, 2001) and by two-stages immobilization in cement stone through 10 M liquid solution NaOH (method NOAH). The last method NOAH was used at NPP SUPERPHENIX in French. Calculated assessments have showed that burial cost of SPO-reprocessed primary sodium in mineral stone is more cheap then cement stone by NOAH method.
STUDY OF DIFFUSION OUTPUT OF IRON FROM EP823 STEEL INTO LEAD MELT
Authors: Ivanov K , Askhadullin R , Osipov A , Niyazov S-A
Published: January 2022

The problem of taking into account the release of metallic impurities from steels into heavy heat carriers is important from two points of view. First, the intensity of these impurities entering the coolant directly affects its quality, the formation of deposits based on oxides of metal components of structural steels in the primary circuit, as well as contamination of the gas system and the radiation environment. In addition, the process of the entry of metallic impurities into the coolant during the development of the oxidative nature of its interaction with steels determines the kinetics of this interaction and should be taken into account in oxidation models, especially with an increase in the duration of contact between steel and the coolant. At present, in world practice, despite the understanding of the importance of taking into account the losses of metal components of steels into the coolant, there is no adequate physical model for accounting for these losses. Basically, one or another empirical or semi-empirical approach is proposed. A new experimental data processing technique to verify the model of the release of iron into the lead coolant is presented in the article. It’s based on the analysis of the deoxidizing stage of the process of regulating oxygen TDA in the volume of the coolant. Series of experiments was carried out with varying temperature conditions in the range from 500 to 635 °C and the oxygen mode of CO = (1 ÷ 4) 10-6 wt%. It is shown that the diffusion models of iron yield and oxygen consumption describe well the experimental results and can be used in calculation codes for mass transfer in circuits with HLMC. The numerical values of the parameters characterizing the yield of iron in HLMC depending on the TDA of oxygen and the temperature of the liquid metal under conditions of natural convection are obtained.
MATHEMATICAL MODEL OF PRIMARY RADIATION DAMAGE TO THE BOROSILICATE GLASS INTENDED FOR IMMOBILIZATION OF RADIOACTIVE WASTE
Authors: Sinyukov R , Blokhin P , Pryanichnikov A , Simakov A , Belikhin M , Degtyarev I , Novoskoltsev F , Altukhova E , Altukhov Yu , Blokhin A
Published: January 2022

The paper describes the physical basis of the mathematical model of radiation-ion damage in solid matter. The following stages of defect generation are considered: primary knocked out atoms, atomic collision cascades (dynamic stage of damage formation) based on 6 types of cascade functions. The software implementation of the described model is included in the RTS&T code designed for statistical modeling of multi-particle (200 types of particles, resonances and ions) radiation transport in heterogeneous 3D geometries in the energy range up to 20 TeV. In the region of low energies, the RTS&T transfer model is based on direct use of all the information contained in the evaluated nuclear data files submitted in the ENDF-6 format. The report compares the results of numerical modeling with experimental data.
PROGRAM “NUCLEAR CALCULATOR EGP-6” FOR ENGINEERING CALCULATIONS OF RADIATION CHARACTERISTICS OF BILIBIN NPP
Authors: Zherdev G , Suvorov A
Published: January 2022

The computer program is intended for design and operational calculations that serve to substantiate the safety of nuclear facilities in documents submitted to ROSTEKHNADZOR and declared as a means of engineering calculations of radiation characteristics of spent fuel assemblies declared in the following topics: calculation of radiation protection and radiation safety of nuclear facilities; neutron-physical calculations (nuclide composition calculations). The computer program can be used independently or as part of other software systems for calculating the characteristics of objects consisting of spent fuel assemblies of uranium-graphite reactors EGP-6, AMB and AM and / or their parts. Computer program Nuclear Calculator EGP-6 2.0 is a set of WIMS-D5B and ORIGEN-S programs, as well as a number of auxiliary programs that provide both the preparation of initial data for the above programs and their interaction, and the processing of results to obtain radiation characteristics. The program has been thoroughly verified and validated. Today the program is a working tool for engineering and operational calculations, focused on the end user. Uses simple and straightforward inputs. The results are prepared in the format required by the customer. The state registration of the program was carried out.
A PROGRAM COMPLEX KIR VERIFICATION ON CRITICAL EXPERIMENTS WITH SOLUTION ASSEMBLIES
Authors: Gomin E , Davidenko V , Shirokov R
Published: January 2022

The article presents the results of testing the KIR code designed to solve the neutron transfer equation by the Monte Carlo method, based on available experimental data from the international Bank ICSBEP on solution benchmarks. The KIR program is part of the DAREUS program complex designed for modeling dynamic processes in solution reactors. Computer models of 13 critical assemblies were created. The total number of calculated configurations was 137. The results were analyzed and the calculation errors were determined both in comparison with the experiment and with other programs. In most cases, the calculated keff multiplication factor falls within the experimental error. The obtained calculation results show a mean square deviation of the multiplication coefficient of 0.7 % for all calculated configurations of experimental assemblies. However, for a number of assemblies, there are significant differences in the assessment. Similar deviations in the calculated values of keff were observed in a variety of previously performed calculations for other codes. The article presents the main factors affecting the results of calculations. Mainly they are related to the insufficiently complete description of experiments submitted to the ICSBEP International Bank.
ADVANTAGES OF THE FAST REACTOR CORE SURROUNDED BY THE PHYSICALLY THICK NEUTRON REFLECTOR MADE OF LEAD-208
Authors: Shmelev A , Apse V , Kulikov G , Kulikov E
Published: January 2022

The paper analyzes the effects produced by the use of lead isotope 208Pb instead of natural lead as a coolant and neutron reflector on neutron-physical parameters of fast reactor. A possibility is demonstrated to reach substantial (up to three orders of magnitude) elongation of mean prompt neutron lifetime in the fast reactor with physically thick 208Pb-reflector. So large elongation of prompt neutron lifetime opens an opportunity for remarkable enhancement of the reactor safety under conditions of reactivity-induced accidents. Numerical analyses have shown that it became possible to form high flux of slowed down and epithermal neutrons in 208Pb-reflector even at large distances from the reactor core. Spacious area of high neutron flux out of the reactor core may be used to transmute long-lived fission products and to produce significant quantities of necessary isotopes. Weak neutron absorption in 208Pb makes it possible to reach remarkable (up to 20 %) reduction of plutonium fraction in mixed uranium-plutonium fuel composition. It is proposed to place a layer with neutron absorber in 208Pb-reflector above the reactor core for the reactivity control with no variations in neutron-physical properties of the reactor core. If reactivity of the control rods in the reactor core is lower than effective fraction of delayed neutrons, then the reactor is obviously subcritical on prompt neutrons of the reactor core. In this case the danger of the reactivity-induced accident on prompt neutrons of the reactor core disappears. If the reactivity-induced accident is caused by joint action of the neutrons produced in the reactor core and in 208Pb-reflector, then the accident propagation will be substantially slowed down because of the longer lifetime of neutrons in 208Pb-reflector.
THERMOPHYSICAL INVESTIGATIONS: FROM THE FIRST TO STAND LARGE-SCALE NUCLEAR ENERGY
Authors: Kuzina Ju , Arnoldov M , Orlov Yu , Sorokin A
Published: January 2022

The article presents the main research results of thermal physicists of the IPPE from its inception to the present time. Research results in the areas of heat and mass transfer and hydrodynamics of coolants (liquid metals, water), physical chemistry and technology of liquid metal coolants for nuclear power plants for various purposes (nuclear power plants, nuclear submarines, space nuclear power plants), development codes, innovative projects, non-nuclear technologies for the use of liquid metals, heat pipes, analysis and generalization of thermophysical data are considered in the article. As a result of a large complex of experimental and computational studies, the fundamental physicochemical and thermohydraulic regularities of the coolant - impurities - structural materials - protective gas have been studied, scientific foundations have been created for the use of liquid metal coolants in nuclear power. Studies have been carried out to substantiate the technical and economic characteristics of nuclear fuel for operating, under construction and future NPPs of VVER RP, design solutions for passive safety, technical solutions and hydrogen safety devices, heat removal from the reactor through a steam generator and PHRS in case of beyond design basis accidents. As well as design solutions and safety for NPP designs with BN-1200 reactor with sodium coolant, BREST-OD-300 reactor with lead coolant, SVBR-100 reactor with lead-bismuth alloy, MBIR research reactor. The results of these studies made it possible, together with institutes and design organizations, to scientifically substantiate thermal-hydraulic parameters and highly efficient technological processes, develop and practically implement devices and systems that ensure the successful operation of fundamentally new nuclear power plants cooled by water and liquid metals, with original scientific and technical solutions that had no analogue in world practice. R&D works were carried out to substantiate the innovative project VVER with supercritical pressure, the concept of an electro-nuclear subcritical blanket based on the modular principle of constructing an core with liquid-salt melts of fissile materials, studies of thermal hydraulics, mass transfer of high-temperature sodium and the development of a combined coolant purification system to justify the BN-HT reactor with temperature sodium ~900 °C for hydrogen production. The directions of investigations at the present stage are discussed.
CHOICE OF THE STRUCTURE OF A TWO-COMPONENT NES WITH OPTIMAL TAKING INTO ACCOUNT AN EXPORT POTENTIAL AND TECHNICAL AND ECONOMIC INDICATORS
Authors: Zrodnikov A , Korobeinikov V , Moseev A , Egorov A , Decusar V
Published: January 2022

In accordance with the approved order of the State Atomic Energy Corporation Rosatom dated May 24, 2018 No. 1-1/366-r “Strategy for the development of nuclear power until 2050 and the outlook for the period up to 2100”, the transition to a two-component structure of nuclear power in Russia is a key area of its technological development. The structure of a two-component nuclear power system (hereinafter NES) can include various elements, the search for the optimal combination of which in development is a multi-parameter problem. The relevance of determining the appearance and structure of a two-component NES is that it is designed to ensure sustainable, cost-effective electricity production in the face of growing global restrictions on natural resources of fossil fuel and environmentally harmful emissions, while meeting the requirements of nuclear, radiation safety and nuclear non-proliferation, as well as to realize the potential increasing the commercial attractiveness of the nuclear industry through the provision of services in the field of nuclear fuel cycle. The article presents the results of computational and analytical studies to substantiate the creation of a two-component NES and recommendations for choosing the structure of a two-component NES with optimal technical and economic indicators, taking into account the export potential. To select the optimal scenario for the development of a nuclear power plant, a multi-criteria analysis of the simulation results with a given set of system criteria was carried out.
MATHEMATICAL ANALYSIS OF AIRCRAFT TURBINE COLLISION WITH SHIPPING PACKAGE
Authors: Vilenskii O , Dushev S , Lapshin D , Novinskii E , Tatarskii A
Published: January 2022

The aim of the paper is to substantiate the developed shipping package integrity on the basis of mathematical analysis of postulated scenarios for the heaviest dynamic effects using verified behavior models for applied structural materials and modern certified finite element software package. The shipping package is permitted to transfer to the limiting condition in the result of impact, when its further operation is not acceptable, and recovery of its functional condition is not expedient, excluding the possibility of falling out of the nuclear fuel (NF) or distortion of the relative position of the NF in the shipping package. The paper presents main analysis results of the process of an aircraft turbine collision with a shipping package. The calculation analysis was performed using the dynamic calculation module LS-DYNA of the certified software package ANSYS. The LS-DYNA module is meant for computational analysis of high linear dynamic processes under explicit scheme of integration of the dynamics equations. The completed full-scale mathematical 3D modeling permitted to carry out sufficiently deep and detailed analysis of dynamic processes, reducing the design duration, and it permitted to reduce the self-cost of the developed design. The obtained results of mathematical analysis of shipping package behavior during interaction with aircraft turbine enabled to form the approach to substantiation of equipment safety in incidents. The detailed design study performed at the design stage formed basis for the final appearance of the developed structure.
NUMERICAL AND ANALYTICAL STUDY OF THE FORMATION AND ACCUMULATION OF DEPOSITS ON THE CIRCUIT WITH HLMC WITHIN THE CONSISTENT MODEL FOR PHYSICAL AND CHEMICAL PROCESSES
Authors: Avdeenkov A , Achakovskiy O
Published: January 2022

An engineering model has been analyzed for a self-consistent calculation of the growth of an oxide film in circulation circuits with a heavy liquid metal coolant and concentrations of impurities (oxygen, iron, and magnetite) from the point of view of a possible uncertainty in determining the oxygen activity. The modeling of thermohydraulic and physicochemical processes is based on solving the associated three-dimensional equations of hydrodynamics, heat transfer, convective-diffusive transport, and the formation of chemically interacting impurity components in the coolant volume and on the surface of steels. The yield of iron and the formation of magnetite are due precisely to the specifics of self-consistent physicochemical processes in the oxide film and at the interface. There have been conducted model calculations of the influence of the uncertainty of oxygen activity on the speed and the integral yield of iron, which under the given conditions of the oxygen regime after an interaction with oxygen causes the appearance of magnetite. It has been numerically demonstrated that in the saturation mode there is a model-independent characteristic, which is determined by the parabolic constant and thickness of the oxide film characteristic of steel.
KORSAR/GP AND SOCRAT/V1 CODES’ VALIDATION FOR THE LOSS OF COOLING AT SPENT FUEL POOL CONDITIONS
Authors: Bedretdinov M , Stepanov O
Published: January 2022

The results of experiments on boiling off a coolant in the assembly of rods ADELA-2 and ALADIN test facility were considered in the article. During the work, the ADELA-2 and ALADIN test facilities were simulated using the KORSAR/GP and SOCRAT/V1 thermal-hydraulic codes. The effect of the degree of spatial discretization on the calculation results was estimated and it was shown that the results of the calculated data are in acceptably good accordance with the experimental data. The results obtained demonstrate insignificant errors in determining the time of uncovering the rods and reaching the maximum temperature. The computer code’s results in most cases are more conservative than experimental. The effect of earlier uncovering of less powerful fuel assemblies in ALADIN experiment is detected. It is confirmed by the results of calculations. This effect should be taken into attention when analyzing safety in emergency modes with spent fuel pool heat removal system failure.
RESEARCH OF TIME DEPENDENCE OF DELAYED NEUTRON INTENSITY FOR THE FISSION OF 237Np WITH DIFFERENT EXCITATION ENERGY
Authors: Egorov A , Gremyachkin D , Piksaikin V , Mitrofanov K , Mitrofanov V , Kobets U , Kolesnikov D , Chaplygin E , Matveev O , Sutyagin I
Published: January 2022

Development of the technologies of nuclear energy utilization, particularly involving of the minor actinides nuclides in the fuel cycle, due to the differences of time characteristics of the fissioning systems and the number of neutrons emitted by nuclides in the fission process, including its growth with the growth of primary neutron energy require the increase of accuracy and the volume of nuclear data. In the present work the behavior of the time dependence of delayed neutron intensity is studied for the neutron induced fission of the 237Np with the growth of the excitation energy. In the process of the comparative analysis there have been used the data calculated using GEF code and experimental data. Comparative analysis of the mass distributions of fission fragments for the fission of 237Np by neutrons with energies 1 and 18 MeV shows the difference in the magnitude of the separate masses from 15 times in the region of the asymmetric fission to 100 times in the region of the symmetric fission, that is the evidence of the differences in the time behavior of the decay curves of delayed neutron intensity. Using the set-up, that allows registering the delayed neutrons, installed of the neutron-physical research channel of Tandem-3M accelerator there have been made the measurement of the decay curves of delayed neutron intensity using the primary neutrons with different energy.
SPECIFICS OF HEAT TRANSFER AND HYDRODYNAMICS DURING MOLTEN SALT IMITATOR FLOW IN A DUCT
Authors: Belavina E , Belyaev I , Pyatnitskaya N , Sorokin A
Published: January 2022

The possibility of using molten salts based on fluorides as a coolant in promising developments in nuclear power systems requires solving several key scientific and technical problems. These problems are associated with development of reliable structural materials and study of thermophysical characteristics of coolant. Solution to the latter problem was constrained by lack of reliable systematic data on physical and chemical properties, specificity of heat transfer processes, and operation technology of promising compositions of fluoride molten salt. In this regard, a comprehensive study, consisting of studying properties of promising fluoride salt melts, as well as creating an experimental base for verification of engineering calculations, is of particular interest for design of reactor facilities. In course of the work, specifics of interaction of electromagnetic forces and buoyancy forces during MHD heat transfer of molten salt, which can manifest itself in the formation of local overheating points or quasi-stationary flow regimes accompanied by low-frequency temperature fluctuations, were experimentally investigated. For first time, dependences of heat transfer coefficients in a stream under influence of a magnetic field in an extended range of operating parameters were experimentally obtained. The results are compared with known patterns and numerical modeling.
Analisis Gaya Bahasa Perulangan pada Lirik Lagu dalam Album Monokrom Karya Tulus dan Implikasinya Terhadap Pembelajaran Bahasa Indonesia di SMA
Authors: Rosdiana Rina , Putri Ega Septiani
Published: January 2022

Language is very close to human life because language is able to convey a message through spoken words, especially in song lyrics that have the same characteristics as poetry, this is certainly contains a diverse language style. This study aims to find out the use of language styles on song lyrics in a monochrome album of Tulus. Not only about that, this also aims to know the implications of using language styles in learning Indonesian in Senior high school. The writer uses qualitative descriptive method in this research techniques that refers to the theories of the experts. The research data used in conducting the research is to use excerpts the lyrics of song containing repetitive language styles such as simploke, chiasm, epizeukis and anaphora. Moreover, the data that has been collected will be analyzed and described. The result of the language styles analysis in the lyrics of the song are found 68 quotes, including simploke 13, chiasmus 39, epizeukis 6, and anafora 8. The results of this study can be used as teaching material innovation in Indonesian language learning in senior high school because the language styles materials are learned by the senior high school students. The use of repetitive language styles has an important connection to suppressing meaning, so students are able to express their message. However, from 10 songs on the monochrome album, it can be concluded that the song has more chiasm. Chiasm is a style of language in which there are two different words but it can have the same or different meaning.