bluuebunny/crossref_metadata_2025 huggingface dataset:
USING PARTIAL EQUATIONS FOR ANALYSIS OF THE FAST BREEDER REACTOR KINETICS
Authors: Seleznev E , Bereznev V , Chernova I , Belov A
Published: January 2022

To analyze the possibilities of using the system of partial neutron transport equations in evaluating the kinetics of a fast breeder reactors compared to the classical system of equations, computational studies of test models of MET-1000 and MOX-1000 reactors developed in the framework of the Generation-IV. As transient processes, the displacements (dumping and lifting) of control rods were simulated, and the reactivity effects in the indicated reactors were evaluated through the solution of stationary problems, i.e. through the use of an asymptotic estimate of the reactivity obtained from the solution of the stationary eigenvalue problem and from the processing of the inverse solution kinetic equation method from solving the transient problem. Test calculations were carried out in 26 and 28 group approximations using the BNAB-93 and BNAB-RF libraries and eight groups of delayed neutrons. The article shows that the features of determining, both calculation and measurement, the effects of reactivity and efficiency of control rods in fast breeder reactors are related to the working region of the neutron spectrum.
PRE-PROCESSOR DIFFUSION CODE DOLCE VITA
Authors: Drobyshev Yu , Seleznev E , Bereznev V , Dovgopoly A
Published: January 2022

The diffusion neutron-physical code for detailed calculation DOLCE VITA is designed to solve state-of-the-art problems of existing and under developed fast breeder reactors. Main advantages of the program is the diversity of calculation channel for each assembly in the reactor load. Meanwhile increasing the number of assemblies types leads to a significant increase in the amount of stored information. To provide to user manipulation ability to both the of the simulated object and the task a pre-processor has been developed. The main purpose is to prepare sufficient data about position, size and calculation node composition to perform calculation. The pre-processor is based on the “constructor” technology of the core with analogue of which is used for the automated preparation of constants for large scale training system. Data is stored in a hierarchical structure in a database. An assembly is represented by number of fuel elements, which consists of a number of cylindrical or hexagonal surfaces filled with material containing number of any nuclides with a specified temperature. To prepare nuclear concentrations for each of the calculation node of a heterogeneously represented assembly in DOLCE VITA is used service script for the database which automatically makes the homogeneous concentration of the one. In the paper is provided an example of calculation task preparation for the DOLCE VITA code with number reactors from a set of benchmarks of 4th generation fast-neutron spectrum nuclear reactors.
SCWR DEVELOPMENT FROM CONCEPT TO TEST REACTOR
Authors: Glebov A , Baranaev Yu , Moskovchenko I , Kirillov P
Published: January 2022

The nuclear reactor cooled by supercritical pressure water - SCWR (Supercritical Water-cooled Reactor) is adopted as one of the promising reactors of the IV-generation. SCWR conceptual proposals are developed by more than 45 organizations in 16 countries with developed nuclear energy. The SCWR concept is based on the implementation of a single-circuit direct-flow scheme of nuclear power plants cooled by SKD water. The introduction of reactors of this type will increase the efficiency up to 45 %, increase the coefficient of fuel reproduction, reduce metal consumption and construction volumes, improve economic and environmental performance. Countries participating in the MFP in the direction of SCWR consider the development of a reactor with a thermal spectrum of neutrons and uranium fuel to be a priority, but in the subsequent stages, with an increase in problems with the storage of spent nuclear fuel (SNF) and Junior actinides (MA), it is possible to move to a reactor with a fast neutron spectrum, MOX fuel and a closed fuel cycle (ZTC). For ~10 years, the SSC RF - FEI and OKB "Gidropress" have been working together on the conceptual design of VVER-SKD - single-circuit RP with SCD coolant with a fast-resonance neutron spectrum with a capacity of Ne=1700 MW. This rector is recognized as the prospect of development of VVER technology with the possibility of using uranium fuel and the transition in the future to MOX-based fuel (U-Pu-Th) and to ZTZ. Rosatom recognizes this area as an innovative one, and has signed systemic agreements on Russia's participation in the work of the MFP in the SCWR direction. The paper presents the results of computational studies on the main version of the high-power reactor, as well as the test N=30 MW.
COMPARISON OF THE INFLUENCE FACTORS FOR THE CALCULATION CURRENTS OF THE IONIZATION CHAMBER FOR THE REACTOR RP V-392M (VVER-1200), CALCULATED IN VARIOUS WAYS
Authors: Kulikov V , Semenova T , Zhylmaganbetov N , Popykin A , Smirnova A
Published: January 2022

The article represents the results of calculations of the influence factors of fuel assemblies on the current of ionizing chambers (IC) in the simulation of a reaktimetr of reactor VVER. Two independent approaches and two programs were used to solve the neutron transport equation. The influence factors of the extreme series of fuel assemblies nearest to the reflection shield and IC on the IC readings are calculated. According to the known software "MCNP-4C" factors are obtained from the solution of forward and adjoint problems. Software "TDMCC", developed in RFNC-VNIIEF, the influence factors obtained from the solution of the forward problem. Both of programs implement the Monte Carlo method to solve the transport equation. The obtained coefficients were used in the calculations of measurements that were carried out at the physical start-up of unit 1 of Novovoronezh-2 NPP, including the simulation of measurement of scram-system efficiency. The article represents the dependence of the relative current on time in the logarithmic scale, as well as the dependence of reactivity on time, built on the results of numerical simulation using three sets of the influence factors in the process of resetting the scram-system. As an illustration, the dependencies are not different from each other.
IMPACT ASSESSMENT OF COOLANT DENSITY VARIATION ON THE ACCURACY OF VVER ENERGY RELEASE CALCULATION
Authors: Artemov V , Kuznetsov A , Kurakin K , Tikhomirov A
Published: January 2022

This paper presents the verification results of SAPFIR_95&RC_micro program that is intended for fine-grid three-dimensional pin-by-pin calculation of power in VVER reactor core at change of coolant density. In this paper, fine-grid three-dimensional pin-by-pin power calculation is typically seen as calculation where pin-by-pin power is computed on the finite-difference grid that matches the fuel rod spac-ing in fuel assembly. MCNP-based calculation was used as a benchmark; this calculation was prepared for one of the first fuel loadings of the NPP-2006 reactor. A series of two-dimensional calculations has been performed: in each test the same coolant density over the reactor core (variation of water density from 0.3 to 0.8 g/cm3) is set, coolant temperature is considered as invariable and is 315 °C. Three-dimensional calculation has been performed: different density (range of 0.46-0.73 g/cm3) in ten layers along the core axis is set, coolant temperature is varying from 299 to 348 °C. The influence of number of energy groups on the accuracy of power calculation for fuel rods and gadolinium fuel rods is analyzed. Two-, six- and twelve-group diffusion approximation are calculated. The calculation model is prepared using SAPFIR_95.1 cell calculation program and SAPFIR_95&RC_micro pin-by-pin power calculation program.
CALCULATION OF SELF-POWERED DETECTORS RESPONSE BY MEANS OF THE MCU-PD AND TVS-M CODES
Authors: Bikeev A , Kurchenkov A , Shkarovsky D , Shkityr V
Published: January 2022

For successful licensing and safe passage of pilot operation of a new type of fuel in the core of an operating VVER-1000 reactor, it is necessary to carry out a preliminary validation of design codes that are routinely used for developing fuel cycles, core safety analysis and calculating maintenance of power unit operation. Validation matrix of the design codes includes problems of calculating transition functions of self-powered neutron detector (SPND). SPNDs are the part of incore monitoring system, which allows to determine power density in the core of an operating power unit. Transition functions from the self-powered detector current to the power density are calculated by means of TVS-M spectrum code. For each type of FA and each instance of self-powered detectors, transition functions are calculated in advance. Transition functions are never corrected during operation, therefore, strict requirements are imposed to the accuracy of their calculation. The main objective of the work is a comparative analysis of the TVS-M spectrum code and the MCU-PD Monte Carlo code as applied to the calculation of transition functions of self-powered neutron detectors for VVER fuel assemblies. During the work, we created calculation models of several types of fuel assemblies, differ in type of fuel, presence of fuel rods with Gd, and placement of SPND. We performed several series of calculations of the created FAs at different burnup steps. The calculations were carried out in states with different coolant parameters, fuel temperatures and presence of control rods. As the target functionals, we considered SPND current, SPND transition function and power density factor of six fuel rods surrounding SPND. We determined maximum relative deviations of TVS-M from MCU-PD in the target functionals calculation. We confirmed acceptable accuracy of calculations of the target functionals by means of TVS-M code for wide range of reactor parameters. We also estimated the influence of homogenization of the SPND structure on the accuracy of transition function calculation.
RESULTS OF MODELING THE OUTPUT OF THE REACTOR BN-800 ON THE MINIMUM CONTROLLED POWER LEVEL AFTER COMPLETION OF 5 MICROCAMPAIGN
Authors: Seleznev E , Belov A , Drobishev Yu , Ivanov A , Mitrofanov S , Kuzmin A
Published: January 2022

The paper presents the simulation results of the BN-800 reactor being placed in a critical state upon completion of 5 microcampaign when detectors are placed inside the reactor building in the vicinity of discharge elevators with a demonstration of signal levels in off-threshold (based on 235U) and threshold (based on 238U) detectors. The calculated data are supplemented by experimental signals from non-threshold detectors located in the same region of the reactor. The computational simulation of the reactor exit to the critical state was carried out using three algorithms: the method of point kinetics; by solving a non-uniform stationary equation with an external neutron source; by solving a non-stationary equation with a space-time dependence of the neutron flux density, taking into account the presence of an external neutron source in the reactor. In addition to directly evaluating the calculated behavior of the reactor power in the simulated process, the features of the used solution algorithms are analyzed.
DEVELOPMENT OF NUCLEAR POWER IN RUSSIA AND THE WORLD WITH GENERATION 3+ AND 4 REACTORS
Authors: Glebov A
Published: January 2022

In the development of nuclear power in the world, there are three stages separated by major accidents at nuclear power plants: "Three Mile Island" (USA, 1979), the Chernobyl nuclear power plant (USSR - Ukraine, 1986) and the "Kama-1" nuclear power plant (Japan, 2011). At the first and second stages, until 1990, there was a rapid development of nuclear power, when 20-30 units were introduced per year and their number increased to 391 with a total capacity of 321 GW, followed by a sharp decline, the withdrawal of many units from operation, which reached the deadline of 40 years. So for after Fukushima Daiichi nuclear disaster from 2011 to 2016, taking into account the withdrawn (17 blocks), only 7 blocks and 13 GW of energy were added. As a result, as of 01.12.2016, the total installed capacity of 450 units was 392 GW. At the same time, prices for uranium and gas have decreased, and the latter has led to an increase in the competitiveness of gas thermal power plants (CCGT with an efficiency of up to 55-65 %). The share of world electricity production at nuclear power plants fell from 17.6 % (1995) to 10.7 % (2015). To improve the nuclear power plant's economy, it was necessary to significantly increase the level of safety while simplifying and reducing the cost of the actual projects, first of all, the reactor compartment (nuclear island-Yao), the cost of power unit equipment, construction and installation on site, and reducing operating costs. As a result, "Generation -3+" reactors were developed and are already being built: Westinghouse (USA) AR-1000, ARR-1400 (Korea), boiling-GeneralElectric (USA) ESBWR- 1650, Areva (France) EPR (1600 mw), in Russia Rosatom - NPP-2006 (1200 mw) and VVER-TOI (1250 MW). The paper presents the results of comparing the economic efficiency of these projects. In January 2000, at the initiative of the US Department of energy, the "generation IV international forum" (MFP-4) program was launched, the goal of the program was to identify the main areas of R & d for the development of promising 4th-generation nuclear power plants. As a result of the evaluation carried out by a group of leading experts in nuclear energy, six basic concepts of nuclear power plants were selected. In this paper, only three of them are considered: these are reactors cooled with sodium (SFR-BN), lead (LFR-BR), and supercritical pressure water (SCWR-VVER-SKD). SCWR reactors have been most developed abroad. In a number of countries, conceptual projects have been implemented showing the economic efficiency of these reactors by 20-40 % compared to the "P. 3+" reactors. In Russia, in order not to depend on fluctuations in uranium prices, to reduce problems with the storage of spent nuclear fuel (SNF) and the implementation of a closed fuel cycle in the nuclear power industry, BN and BR reactors are being actively developed.
REGULATION STANDARDS FOR PERMISSIBLE DISCHARGES OF A FEW RADIONUCLIDES MIXTURE INTO ATMOSPHERIC AIR UNDER NPP NORMAL OPERATION
Authors: Vukolova A , Dolgikh A , Rusinkevich A
Published: January 2022

The article is focused on the description of the existing order for regulations of standards for permissible and maximum permissible discharges of radioactive pollutants into atmospheric air and (on) discussion of an alternative method for regulations of standards for permissible and maximum permissible discharges, basing on establishment of these standards for a mixture of radioactive materials and not for every radionuclide individually. This method is based on using the radionuclide vector concept and allows to significantly facilitate arrangements of radiation monitoring, to abandon spectrometric methods and to use more simple, cheap and speedy radiometric methods for discharge control. This result corresponds to internationally recognized ALARA principle. The procedure of the establishment of permissible discharge of noble gases mixture for atmospheric discharge of Rostov NPP site is shown in the article as an example. The results of the analysis of noble gases atmospheric discharges of 47 European NPPs with WWER and PWR power units, creation of nuclide vector and application of this vector for calculation of permissible discharge of noble gases mixture for the Rostov NPP are demonstrated.
RADIATION SAFETY EVALUATION OF A TRANSPORT CONTAINER DURING CARTING SPENT NITRIDE URANIUM-PLUTONIUM FUEL OF BN-600 USING THE MCU-FR CODE
Authors: Belov A , Bikeev A , Daichenkova Yu , Shkarovskiy D
Published: January 2022

At present, the BN-600 and BN-800 reactors are used for tests of experimental fuel assemblies containing MOX and MNUP fuels. For transportation of spent fuel assemblies of BN-600 with mixed nitride uranium-plutonium fuel is planned to use a regular transport container containing 35 fuel assemblies. The purpose of the work is to develop a calculation model of the transport container containing 35 fuel assemblies and radiation safety evaluation of the transport container during carting spent MNUP fuel of BN-600 using the MCU-FR Monte Carlo code. The developed model of the experimental fuel assembly is integrated into the developed calculation model of the transport container. The resulting model was used to calculate the equivalent dose rate from sources of ionizing radiation in the fuel. The azimuthal and radial distributions of the equivalent dose rate in the plane of the FA core center were considered. In the course of radiation safety evaluation, it was shown that under normal transportation conditions, the maximum total calculated radiation levels on the container surface are determined by primary photon radiation and do not exceed the established limit of 10 mSv/h under exclusive use. The developed model of the transport container and the calculation results obtained by means of the MCU-FR code will be used to prepare the validation base of the ODETTA calculation code.
A COMPLETE DESCRIPTION OF THE MECHANICS OF TURBULENCE IN A MOVING FLUID
Authors: Shcherbakov S
Published: January 2022

The conditions and mechanisms of events in a moving fluid are analyzed, leading to the apparent disorder of unsteady flow, known as turbulence. The method of analysis is the use of different forms of equations of motion and transfer of characteristics, the selection of stable formations in the flow structure and a description of the interaction between them. The non-trivial results of previous works are used. The transfer and transformation of disturbances of a vortex distributed in the flow is analyzed, the conditions under which insulated tubes with a helical flow appear inside the shear flow. An important condition is the short duration of vortex disturbances. Equations are obtained that describe the interaction of the main shear flow and the vortex tube, the features of which lead to flow instability. The existence of two mechanisms for the development of turbulence is shown - the autogeneration of local decelerations and the instability of stretching of vortex tubes. The self-generation mechanism is the transfer of kinetic energy from the main flow to an annular vortex with the generation of a new annular vortex. This is the main mechanism that ensures the propagation of instability downstream, arises first when the Re number increases. The tensile instability leads to the splitting of the vortex tube into independent sections, the generation of many annular vortices that fill the space and drift in it. The vortex multiplication factor in each generation increases with the Re number and can reach many thousands. The role of ordered unsteady flows in the initiation of turbulence is shown.
MEASUREMENT OF 14 MEV NEUTRONS TRANSMISSION THROUGH LITHIUM HYDRIDE LAYERS WITH TIME-OF-FLIGHT METHOD
Authors: Namakonov V , Andreyev S , Gabbasov D , Moseyeva A , Sergina D
Published: January 2022

The results of experiments on transmission of 14 MeV neutrons through lithium hydride layers of thickness up to 25 cm are presented in the article. The measurements were performed with time-of-flight method on a pulse channel of neutron generator NG-12I. The operating mode of the neutron generator is pulse-periodic. Neutrons passing through the layers of Li hydrides were registered by detector based on a 70×70 mm stilbene crystal scintillator. NIM standard modules were used as measuring equipment. The neutron yield from the generator target was estimated by neutron monitor with a fluorine plastic activation detector. Activity of radiation-exposed neutron activation detectors was measured using a gamma spectrometer with high purity germanium detector (HPGe). The averaged 14 MeV neutrons flux from the target was ∼2⋅108 n/s. The measurement results were used to obtain instrumental neutron spectra for samples of various thicknesses and to estimate coefficients of 14 MeV neutrons passing through the layers of Li hydrides. The obtained results can be used for validation of neutron-physical calculations and for improvement of neutron constants libraries.
RADUGA-TV NEW GENERATION CODE FOR SOLUTION TRANSFER EQUATIONS
Authors: Bass L , Nikolaeva O , Davidenko V , Gaifulin S , Danilov A , Khmylev A
Published: January 2022

The article discusses the issue of the concept of “new generation code”, which has been actively used recently to characterize computer programs designed to solve problems of the transfer of neutrons and gamma quanta in nuclear facilities. As an example of a new generation code developed for solving the multigroup transport equation by the grid (deterministic) method, the first version of the new software package RADUGA-TV is considered, including, in particular, the UNK complex for calculating burnup. The article lists the main features of the RADUGA-TV code: the problems to be solved, the types of constants used, the methods for specifying the geometry of the calculation area, the methods for constructing an unstructured spatial mesh. The possibilities of the postprocessor for processing the obtained solution are presented. The article presents progressive algorithms included in the RADUGA-TV code, including grid schemes and methods for parallelizing computations. The advantages of using unstructured grids, including those consisting of cells of various types, are discussed. Methods for parallelizing computations on hybrid computing systems are considered. The question of the spatial grid decomposition when parallelizing computations on distributed memory systems is considered, as well as the question of organizing parallel computation on such systems. Comparison of the characteristics and capabilities of the RADUGA-TV code and other similar in purpose codes, foreign (ATTILA, AETIUS, ARES, THOR) and domestic ODETTA is performed. It is shown that the RADUGA-TV code is significantly advanced methodically and practically has no analogues. The article was written based on the materials of the report at the conference “Neutronika-19” and contains more detailed information on the issues discussed in the report.
EFFECT OF REPLACING FA STRUCTURAL STEEL ON THE REACTIVITY RESERVE IN THE BN-600 REACTOR
Authors: Gurskaya O , Dzugkoeva E , Korobeynikova L , Mishin V , Stogov V
Published: January 2022

The current program in Russia to increase the fuel consumption of fast reactors and increase its burn-out causes the transition to new structural materials, which, in turn, leads to changes in the neutron-physical characteristics of reactors. In particular, the drop in the reactivity reserve noted in the BN-600 reactor of the Beloyarsk NPP at the end of 76 operational cycles, as will be shown below, is due to the transition to a new type of shell steel with an increased content of nickel, which strongly affects the reactivity. Design support for the operation of the BN-600 and BN-800 fast reactors, as well as the experiments carried out on them, is performed by IPPE. This article presents the results of a calculated analysis of the expected changes in the reactivity reserve at the end of 76 operational cycles when replacing the shell steel in BN-600. In addition, the influence of experimental assemblies located in the core on the reactivity reserve of the BN-600 is analyzed. Analysis of calculations of the actual loading of the BN-600 reactor at 76 operational cycle using the methods of the 1st-order perturbation theory, strict perturbation theory, and the Monte Carlo method showed that a partial transition at 76 operational cycle to EK-164 shell steel leads to a decrease in the reactivity margin by 0.030±0.004 %Δk/k. Replacement of steel for the entire core will reduce the reactivity margin by ~0.12 %Δk/k, which is confirmed by Monte Carlo calculations. The calculated reactivity margin obtained at the end of 76 operational cycles for the hot state of the BN-600 reactor is in good agreement with the measured reactivity margin.
HYDRODYNAMICS OF GAS-LIFT PUMP WITH LEAD COOLANT
Authors: Vereshchagina T , Lemekhov V , Morkin M
Published: January 2022

A gas-lift probe is an element of cladding failure detection system of perspective lead cooled reactor. Its function is local measurement of gaseous fission product activity into coolant and the defective fuel assembly localization. The transit time of gaseous fission products from the defect to the place of activity measurement depends on the flow rate of the coolant through the gas-lift probe. Since most fission products have a short half-life period, their delivery time to the measuring vessel should be minimal. Therefore, the calculation of the flow rate of the coolant, as well as the transit time of gaseous fission products in the lifting path of the gas-lift probe is an actual task. A computational methodology of the hydraulics of the gas-lift probe with a lead coolant is presented in this work. The calculation results of two-phase flow characteristics in a reactor gas-lift probe and in the tested model in NIKIET experimental setup are presented. It is obtained the significant difference between the coolant flow rate in the tested model and in the reactor probe at the same gas flow rate. The reasons for these differences are defined.
APPLICATION OF THE FIRST AND LAST COLLISION METHODS IN ODETTA CODE FOR RADIATION SHIELDING CALCULATIONS
Authors: Bereznev V , Belov A , Koltashev D
Published: January 2022

The research is devoted to the features of radiation shieldind calculations by the deterministic program ODETTA, which is intended for numerical simulation of the neutron and photon transport in shielding compositions of the nuclear facilities and based on the discrete ordinates method and finite element method on unstructured tetrahedral meshes. The article describes the methods of the uncollided radiation component calculations implemented in the ODETTA program for “ray” effect elimination which is typical for discrete ordinates method in weakly scattering media with localized radiation sources. In addition, the first collision method allows to correctly simulating point sources, and the last collision method allows calculating the required functionals at the detection points located outside the computational domain. The implemented methods have been tested on computational benchmarks and experiments, a brief description of which is given in the article. The results obtained were compared with analytical and experimental data, as well as with the results of calculations by the Monte Carlo method within the Scale 6.2.3 software package. The analysis of the influence of the calculated parameters is carried out and conclusions are drawn about the effectiveness of the implemented methods.
ON THE ISSUE OF PLUTONIUM COST IN A TWO-COMPONENT NUCLEAR POWER SYSTEM
Authors: Dekusar V , Gurskaya O
Published: January 2022

A possible approach to accounting for the specific present value of plutonium produced in fast reactors of a two-component nuclear power system (NPS) with thermal and fast reactors is described. The approach is based on taking into account the additional income that can be obtained by selling at the market price the natural uranium released when thermal reactors are replaced with fast reactors with MOX-fuel based on plutonium produced in NPS. At the same time, along with the sale of natural uranium, the sale at market value of other products made on its basis, for example, enriched uranium or fuel assemblies for a thermal reactors, can be considered. Relations between the main fuel characteristics of the considered nuclear reactors and the economic parameters characterizing the efficiency of nuclear reactors and the fuel cycle of a NPS are obtained. Using the methodology described in this paper, a computational study of the specific present value of plutonium in a two-product nuclear power model with commercial sodium high-power fast reactor and VVER-1200 reactors was carried out. The calculation results in all considered cases indicate very significant present value of plutonium. Comparison of the obtained cost of plutonium, which is ultimately based on the energy equivalent of plutonium and uranium, and the cost of plutonium, determined on the basis of the costs of the back-end of the fuel cycle (plutonium extraction from SNF), show the economic efficiency of closing the fuel cycle even at existing uranium prices.
INVESTIGATION OF THE SLAGS ACCUMULATION MECHANISM IN LEAD-CONTAINING COOLANTS LOOPS AND ITS PREVENTION BY HIGH-TEMPERATURE TREATMENT WITH HYDROGEN AND WATER STEAM MIXTURES
Authors: Koshelev M , Ulyanov V , Kharchuk S
Published: January 2022

The results of computational and experimental studies of the properties of lead and lead-bismuth coolants and the mechanism of physicochemical processes occurring in their circulation circuits explain the reasons for the formation of slag deposits based on lead oxide. First of all, this is the uncontrolled interaction of lead and lead-bismuth coolants with gaseous oxygen, which, along with nitrogen, is one of the main components of air. Slag deposits are based on lead oxides, but they also contain a significant amount of unoxidized lead (and bismuth in the case of using a lead-bismuth coolant) bound by a lead oxide framework into a single structure, as well as a small amount of components of construction materials (iron , chrome, nickel). The formation of slags in the circulation loop with a lead-containing coolant has a negative effect on its operation: the flow cross-sections are narrowed; heat transfer surfaces are blocked; the normal operation of pipeline fittings is disrupted. To minimize slag accumulation, it is necessary to limit the contact of the coolant with air oxygen, avoid draining the coolant from the circulation circuit, control whether the circulation circuit is in a depressurized state both during research and during non-working periods, when heating and filling the circuits with a coolant, create and maintain a vacuum. The best way to prevent slag accumulation is periodic hydrogen cleaning of the circuit with gas mixtures "hydrogen - water vapor - inert gas". The greatest cleaning efficiency is achieved when gas mixtures are introduced directly into the coolant flow using gas injection devices. Mechanical devices with moving parts, ejectors, nozzle nozzles can act as gas injection devices.
ESTIMATION OF THE CONSEQUENCE OF THE ITPS FALLS DURING TRANSPORTATION AND PROCESSING (HANDLING) OPERATIONS
Authors: Vilenskii O , Dushev S , Lapshin D , Novinskii E , Rusinov N
Published: January 2022

The main results are presented for the analysis of the process of falling of the in-object transportation packaging set (ITPS) in case of fracture of the fixing or slinging elements and estimation of the consequences of ITPS falling during transportation and processing (handling) operations. The ITPS is permitted to transfer to the limiting condition in the result of falling, 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 ITPS. To reduce the costs at the design stage the following representative calculation research of the ITPS was carried out for dynamic impacts to identify weak points of the design in case of an emergency situation. The computational analysis of falling was carried out using the module for dynamic analysis LS DYNA of ANSYS software, certified by the Rostekhnadzor authorities. LS-DYNA module is designed for computational analysis of highly nonlinear dynamic processes using an explicit integration scheme for dynamic 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 results obtained for different variant of the ITPS falling permitted to analyze the collision process, to determine the values of the plastic deformation appearing in the ITPS elements and to provide recommendations for its modification.
EFFECT OF COATING PROPERTIES ON HEAT TRANSFER DURING COOLING OF HIGH-TEMPERATURE CYLINDRICAL BODIES
Authors: Molotova I , Zabirov A , Vinogradov M , Yagov V , Sorokin A
Published: January 2022

The process of cooling high-temperature bodies in liquids is an important physical process, in particular, for the safety of nuclear plants. After the accident at the Fukushima-1 nuclear power plant in 2011, large-scale research was launched to find a new accident tolerant fuel. Studying the effect of the properties of new materials on heat transfer during cooling in the case of repeated flooding of the active zone and the possibility of accurately predicting the transition temperature to the intensive cooling regime will allow substantiating the choice of a new type of tolerant fuel from the standpoint of thermophysics. The aim of this work was an experimental study of the cooling processes of high-temperature cylindrical bodies made of various metals in liquids, as well as determining the effect of coating properties on heat transfer during cooling. A large experimental data array was obtained on the cooling of cylindrical samples; experiments were carried out on smooth cylinders made of various metals, as well as on copper cylinders with various coatings and different degrees of roughness (gold coating, stainless steel coatings).
Efforts to Reduce Pain Through Ergonomic Exercise and Provision of Soursop Leaves Decovation to Arthritis Patient in Sekaran Village
Authors:   Politeknik Kesehatan Bhakti Mulia, Widiastuti Lafina , Aderita Novi Indah ,   Politeknik Kesehatan Bhakti Mulia
Published: January 2022

Dinas kesehatan tahun 2019 menyatakan penderita gout sebanyak 1400 dari 10 Puskesmas di Klaten, Pukesmas Wonosari sebanyak 100 kasus. Data tersebut menunjukkan gout di Kabupaten Klaten khususnya Kecamatan Wonosari masih cukup tinggi (Dinkes klaten, 2019). Gout menyebabkan masalah salah satunya adalah nyeri. Tujuan penelitian ini adalah mendeskripsikan penatalaksanaan senam ergonomis dan pemberian rebusan daun sirsak dengan masalah keperawatan nyeri akut. Metode pengumpulan data dengan observasi, pengukuran, dan dokumentasi. Instrument menggunakan format asuhan keperawatan medical bedah, lembar observasi, alat GCU. Hasil penelitian didapatkan data pengkajian: subjek mengalami nyeri skala enam, nyeri karena peningkatan kadar asam urat, nyeri pada lutut, pergelangan kaki dan betis, nyeri seperti ditusuk-tusuk, nyeri hilang timbul. Data objektif: kesadaran composmentis TTV: TD: 130/90 mmHg, RR: 20 x/menit, N: 82 x/menit, S: 36,7⁰C, wajah: ekspresi pasien tampak menahan nyeri. Tindakan keperawatan meliputi melakukan pengkajian karakteristik nyeri, melakukan senam ergonomis dan pemberian rebusan daun sirsak. Setelah dilakukan asuhan keperawatan sebanyak tujuh kali kunjungan selama satu minggu didapatkan hasil nyeri menurun dari skala enam menjadi skala 3, hasil pemeriksaan asam urat menurun dengan rentang penurunan 2,2-4,3 mg/dl. Masalah nyeri akut teratasi dan tindakan tersebut efektif untuk mengurangi nyeri.
Penerapan Pendekatan Kontekstual dalam Pembelajaran Keterampilan Menulis Puisi pada Siswa Kelas X SMA PGRI 4 Kota Bogor
Authors: Budiana Sandi , Kamil Muhammad Nur
Published: January 2022

This research aimed are to find out Contextual approach in Learning writing poetry and to find out the difficulties on  students of X grade SMA PGRI 4 Bogor in writing poetry. Experiment method is used in this research. Data collection are test, questionnaire and observation. Students of  X grade SMA PGRI 4 Bogor are population of this research. The sample of this research are experiment and controll class. Experiment treatment is X-2 grade IPA and Controll treatment is and  X-1 IPA 2 . To get the data is obtained through Cluster random sampling. The first hyphothesis is implementation of Contextual Teaching and Learning (CTL) which increases  writing poetry on students of X grade SMA PGRI 4 Bogor. It can proved based on the students’result of pretest and postest in experiment treatment is used Contextual Teaching and Learning (CTL) that is their improvement. Hyphotesis is students of  X  grade SMA PGRI 4 Bogor have barrier in writing poetry that is proved. Based on the result of students’ questionnare, they get barrier in writing poetry that is proved based on the 58,33% percentage, they difficult to choose words around 66,67%, then they difficult to choose vocabulary 66,67%, they use the proper and good words 66,67%, they conveys their feeling and idea to write poetry around 62,50%. Therefore, we concluded that Contextual Teaching and Learning (CTL) improves students to write poetry . Either they write poetry or  they get barrier to write poetry.
Public Speaking and Online Peer Feedback in a Blended Learning EFL Course Environment: Students’ Perceptions
Authors: Mortaji Latifa El
Published: January 2022

This paper reports on a blended learning approach for public speaking in an English as a foreign language (EFL) context. The researcher implemented the course design through reduced weekly face-to-face class sessions and online student interaction using a speech video-based blog. Using a survey conducted at the end of the semester, multiple comments provided for online peer feedback, structured outlines submitted to Turnitin, and instructor’s weekly observation of the students’ presence and performance online, the researcher collected data about the students’ progressive learning of the public speaking skills, peer feedback, and the students’ assessment of each aspect pertaining to the blended learning experience. The qualitative analysis revealed the effectiveness of online peer feedback in public speaking skills development as demonstrated by students’ attainment of course intended learning outcomes, as well as an overall positive student perception towards the blended learning model, with minor reservation of less confident students at the onset of the online implementation phase. 
Reviewer Acknowledgements for International Education Studies, Vol. 15, No. 1
Authors: Lee Chris
Published: January 2022

Reviewer acknowledgements for International Education Studies, Vol. 15, No. 1, 2022.
A BVAR Analysis on Channels of Monetary Policy Transmission in Brazil
Authors: Rocha Francisco J. S. , Magalhaes Marcos R. V. , Brilhante Átila Amaral
Published: January 2022

This article measures the responses of GDP and inflation to a positive shock of the variables that make up the channels of transmission of monetary policy. The results of impulse-response functions of the estimated Bayesian VAR (BVAR) were: an increase in the short-term interest rate (SELIC) leads to a long-term interest rate increasing and consequently a reduction in GDP. Free credit does not have a significant impact on Brazilian GDP, given the low free credit/GDP ratio (Bogdanski et al., 2000). A shock in inflation expectations result in a decreasing trajectory of GDP, a fact consistent with the Fisher effect (Mishkin, 2009); and a shock at SELIC reduces inflation in the first two months, there is no “price puzzle”. A credit shock does not cause significant pressures on inflation. The Inflation does not show a well-defined time path after a shock in asset prices. The decomposition of the variance of the forecast error, in turn, showed that: GDP, in the short term, has its forecast errors explained by its own shocks, 70% on average. However, in the medium term, their forecast errors are explained by their own shocks, around 35%, by inflation shocks, 34%, and by interest rate shocks, 20%. The other transmission channels do not have, in the short and medium terms, significant influence on GDP forecast errors, except the asset prices; and inflation forecast errors are explained, in the short term, mainly by their own shocks, 85% on average. In the medium term, inflation forecast errors are explained 68% by inflation itself, 6% by GDP and the others transmission channels participate individually, with approximately 6%. These results are robust when controlled for commodity prices.
Lo sobrenatural y sus hibridaciones en el primer Lope de Vega: hacia un nuevo género dramático
Authors: Gilabert Gaston
Published: January 2022

La propuesta de un género sobrenatural para englobar las comedias que ponen en su centro elementos maravillosos ayuda a explorar procedimientos compartidos por las fábulas mitológicas, hagiográficas y de magia. Partiendo de este marco, el presente trabajo analiza setenta y cuatro comedias vinculadas al primer Lope de Vega con el objetivo de observar la incidencia que tienen esos elementos trascendentes en los distintos géneros que cultivó, más allá de los tres señalados. El resultado muestra la gran importancia de la maravilla sobrenatural en el crisol del Arte Nuevo, ofrece información acerca de las estrategias dramáticas del Fénix en su fase inicial y explica, mediante la hibridación genérica, cómo se proyecta el teatro renacentista de magos y nigromantes en los grandes espectáculos de tramoya del siglo XVII.
La hibridación genérica en el teatro de Lope de Vega
Authors: Trambaioli Marcella
Published: January 2022

Presentación: la hibridación genérica en el teatro de Lope de Vega
Kincentricity and Indigenous Wellbeing
Authors: Presley Rachel
Published: January 2022

This manuscript explores the rhetorical coupling of food as a holistic health initiative across two Indigenous organizations—Indian Health Services (IHS) and the American Indian Cancer Foundation (AICF). Drawing upon contemporary literatures of rhetorical ecologies, I position “kincentricity” (Salmón, 2000, 2012) as a particularly provocative framework to reconceptualize the body as its own rhetorical ecosystem, contending that Indigenous dimensions of RHM offer radically creative ways to decolonize the body/body politic. My analysis demonstrates theways in which IHS and AICF engage in kincentric logics to repurpose rhetorics of food within the Native medicine wheel, most notably by emphasizing (1) pre-Columbian diets, (2) traditional harvesting and cooking methods, and (3) spiritual food-based rituals—all of which explicitly link tribal food(ways) to bodily wellbeing. Finally, this essay encourages RHM scholars to reorient rhetorical vocabularies and understandings toward more pluralistic and non-Western accounts of health, medicine, and collective wellness.
Journalismusforschung: Disziplin durch Entdisziplinierung. Interdisziplinarität in der Forschung und ihrem Gegenstand – zur Einführung in das Themenheft
Authors: Loosen Wiebke , Nölleke Daniel , Springer Nina
Published: January 2022

Journalismus ist ein genuines Medien- und Öffentlichkeitsphänomen in der Gesellschaft. Dies spiegelt sich auch in der Fülle der disziplinären Perspektiven, die für seine Erforschung fruchtbar gemacht werden können. Was heißt es vor diesem Hintergrund, von interdisziplinärer Journalismusforschung zu sprechen bzw. in welcher Weise zeigt sich eine solche in der wissenschaftlichen Praxis? Und auf welche Herausforderungen eines sich kontinuierlich wandelnden Journalismus, in dem auch selbst mehr und mehr die Rede von interdisziplinärem Arbeiten ist, reagiert sie? Im Lichte dieser Fragen beschäftigen wir uns zunächst mit Wandel als Konstante im Journalismus und einer „neuen Interdisziplinarität” zu seiner Erforschung unter den Bedingungen und Folgen der Digitalisierung. Im Anschluss beleuchten wir den integrativen Charakter der Journalismusforschung und ihre inter- und transdisziplinären Perspektiven. In diese Rahmung ordnen wir die Beiträge des Themenhefts ein. Wir plädieren für eine „ent-disziplinierte Journalismusforschung”, die ihre Stärken mehr und mehr auch in inter- und transdisziplinäre Forschung zum Journalismus und seiner Rolle in der Gesellschaft einbringt und schließen mit einem Überblick über die Beiträge des Themenhefts, die interdisziplinäre Journalismus-Forschungs-Praxis aus ganz unterschiedlichen Perspektiven behandeln.
Socialbots at the Gates. Plädoyer für eine holistische Perspektive auf automatisierte Akteure in der Umwelt des Journalismus
Authors: Muhle Florian
Published: January 2022

Automatisierung ist in den vergangenen Jahren zunehmend in den Fokus der Journalismusforschung gerückt. Allerdings interessiert sich diese bisher vor allem für Automatisierung im Journalismus, aber nicht für Automatisierung in der Umwelt des Journalismus. Der vorliegende Beitrag nimmt sich zum Ziel, dies zu ändern, indem er im Anschluss an Forderungen nach einer holistischen Journalismusforschung dafür argumentiert auch sog. Socialbots, die in der Umwelt des Journalismus in sozialen Medien aktiv sind, zum Gegenstand der Journalismusforschung zu machen. Grundlage hierfür ist die Vermutung, dass die Aktivitäten von Socialbots nicht in erster Linie auf die direkte Beeinflussung von Social-Media-Nutzer*innen zielen, sondern auf die Beeinflussung von Prozessen öffentlicher Themensetzung und Meinungsbildung in einem zunehmend hybriden Mediensystem, in dem sich dauerhafte Interdependenzen zwischen sozialen Medien und traditionellen publizistischen Medien etabliert haben. In dieser Hinsicht erscheinen dann auch Journalist*innen als primäre Adressat*innen von Socialbots, die als interessierte Dritte aufmerksam das kommunikative Geschehen in sozialen Medien beobachten und auswerten.
Microwave Antennas Suggested for Biomedical Implantation
Authors: Sudam Patil Kasturi , Rufus Elizabeth
Published: January 2022

In the twenty-first century, there is an enormous development in various areas: microwave sensors have played an important role in medical devices, because of population growth and public awareness of the health of medical devices, they have become an ever-increasing technology. Microwave antenna sensors can be used to monitor human body temperature, implantable defibrillators, pacemakers, continuous glucose monitoring, heart failure detection, and so on. Antennas are also used as flexible sensors to monitor physiological parameters. Therefore, microwave sensors are used for wireless communication in various biomedical applications. The design of such antennas has gained considerable attention for dealing with issues such as miniaturization, biocompatibility, patient safety, improvement in communication quality, etc. The objective of this paper is to prove an overview of the requirements, design steps, and testing of a microwave antenna used in biomedical implantation. In this chapter, various antennas used in medical applications are described in detail. Also, antenna designing and testing requirements are discussed.
Building New Rural Areas in Vietnam
Authors: Hay Nguyen , Quang Huy Le , Van Kien Pham
Published: January 2022

The study focused on the orientations of building sustainable new rural areas associated with urbanization. This was very necessary, in order to develop a concentrated, commodity agriculture and to form residential areas and infrastructure, which were suitable to the process of industrialization and modernization of agriculture and rural areas. The agricultural sector was restructured, and the living conditions of rural people were improved close to those in urban areas. The project of the National Target Program on building new rural areas in Vietnam was analyzed. The program has achieved many expected results. In which, the construction of new rural areas has achieved great achievements. The basic socioeconomic infrastructure in the rural areas was strengthened in a synchronous direction. The sustainable development of the rural economy was in the direction of increasing added values and raised people’s incomes and gradually narrowed the gap between rural and urban areas. The work of landscape construction, implementation of environmental sanitation had a remarkable change.