


卷 120, 编号 1 (2016)
- 年: 2016
- 文章: 12
- URL: https://journal-vniispk.ru/1063-4258/issue/view/15475
Article
Analysis of the Consequences of an Accident with Damage to a Horizontal Experimental Channel During IR-8 Operation at Nominal Power
摘要
The consequences of postulated beyond design-basis accidents in the IR-8 reactor are now being analyzed. Since the development and construction of a three-dimensional model of IR-8 the ATHLET systems code has been used to perform computational thermohydraulic analysis of the consequences of an accident involving damage to a horizontal experimental channel. The maximum possible dewatering of fuel assemblies in the core (42 cm) with a leak appearing in a 100 mm in diameter channel due to a 2.5 mm gap opening along the entire perimeter, which could be due to the failure (detachment) of the bottom plate, is analyzed.



Development of a Computational Reactor Model in the IR Program Based on Experimental Data on Xenon Power Oscillations
摘要
A method of improving the computational reactor model in the IR program on the basis of the experimental data on the xenon power oscillations is presented. It is concluded on the basis of the deviation of the computed axial offset from experiment that the program requires adjustment. The program was modernized by replacing the dependence of the thermophysical parameters of the core on the specific rate of power release by solving the heat-conduction and heat-and-mass transfer equations. This is accomplished by means of the method and software used in the NOSTRA computer code, which were additionally improved by taking account of the influence of structural changes in the fuel on the thermal conductivity.



Calculation of Design-Basis Accidents Loss of Coolant Circulation for the IRT MIFI Reactor
摘要
The results of calculations of emergency situations for the IRT MIFI [Moscow Engineering Physics Institute] reactor with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel cores based on the alloy U–9%Mo in an aluminum matrix with 19.7% enrichment are presented. The transient processes due to disruption of coolant circulation during the execution of safety functions are examined. The PARET 7.5 software is used to calculate the transient processes. Special attention is focused on taking account of emergency protection engagement algorithms and the characteristic features of the devices monitoring the thermohydraulic parameters of the reactor in setting the initial data for the calculation of transient processes.



Evaluation of the Effect of Thermal Stratification on the Residual Life of the Surge Line of the Pressure Compensator in the No. 5 Unit of the Novovoronezh NPP
摘要
This article is concerned with investigations of temperature stratification of the first-loop coolant in the surge line of the pressure compensator in the No. 5 unit of the Novovoronezh NPP. The actual stress-strain state and accumulated structural damage in the surge line in different operating regimes was analyzed by means of multiparametric computational and experimental monitoring. The experimental data demonstrate thermal stratification, giving rise to a temperature differential over the cross section ranging from 30°C under normal operating conditions to 150°C, as a result of disruption of the normal operating conditions, and high thermal stresses. The analysis shows that the cyclic strength of the weld connection of the surge line can be exhausted by the end of the 60-yr life of the No. 5 unit. It is concluded that the actual residual stresses must be measured and calculations of the cyclic strength and the residual life of the surge line must be performed. It is suggested that a technology be developed to strengthen the weld-joint metal in order to reduce the formation of operational surface defects.



Development of a Multidimensional Method for the Interaction of Liquid–Gas Two-Phase Flows with Formation of an Interphase Boundary
摘要
A method of evaluating the liquid–gas interaction with the formation of an interphase boundary is presented. The method is verified on modeling of the propagation of a shock wave in a liquid medium with gas bubbles. Good agreement with experiment is obtained. The results of numerical modeling of the downward flow of a liquid over a stationary gas bubble are presented. Verification of the method will be continued on experiments with a model coolant.



Optimization of Electric-Pulse Consolidation Regimes to Obtain High-Density Dispersion-Hardened Reactor Steel
摘要
Research on the development of EP-450 high-density, Y2O3-oxide dispersion-hardened, reactor ferritemartensite steel is described. All available parameters influencing the final density of the compacts were varied in the course of the preparation of the powders and electric-pulse consolidation. The research established that samples with density equal to 99% of the theoretical value can be obtained for the following optimized mechanical activation and electric-pulse consolidation parameters: mechanical alloying time 30 h, optimal Y2O3 amount 0.2–0.5 wt.%, sintering temperature 825–890°C, climb rate to the prescribed temperature >300°C/min, load 70–80 MPa, holding time at the load – without isothermal holding or holding for ≥3 min.



Methods of Inspecting the Radioactive Contamination of Uranium-Graphite Reactor Masonry
摘要
One problem of decommissioning graphite reactors is the evaluation of the radioactive contamination of the graphite. The possible methods of determining the composition, contamination, and radionuclide concentration by means of laboratory analysis of graphite samples taken from the reactor masonry are examined. It is proposed that samples of graphite powder formed during repair work performed on RBMK masonry be used. Life tests have shown that since their operational stability in neutron and γ radiation fields is adequate CdZnTe detectors can be used to probe the channels in the reactor masonry.



Comparative Method of Calculating the Thermodynamic Parameters of Some Uranium Hexafluoride Solutions
摘要
It is shown that the thermodynamics characteristics of uranium hexafluoride solutions with volatile hexaand pentafluoride elements are a consequence of the strictly symmetric configuration of their molecular structure in the gaseous and liquid states. Simple methods are proposed for evaluating the properties of binary mixtures of elemental penta- and hexafluorides. These methods are based on a comparison of the element–fluorine bond length in the constituent molecules of system and the known enthalpy of mixing of one solution with the potential energy in the formation of a pair of unlike molecules of a different solution.



Benchmark Experiments for Verifying the Working Parameters of the Blankets of a Thermonuclear Neutron Source
摘要
The possibility of verifying benchmark experiments which are necessary for design validation of the blankets of the TIN-ST thermonuclear neutron source based on the I-2 proton accelerator using neutrons from the reaction 7Li(p, n) is analyzed. It is shown that modern software and databases are effective in calculating the neutron spectra for two types of thorium blankets: solid-state and molten-salt. The hardware and procedures used to develop an adequate idea of the spectral characteristics of the neutron fluxes from plasma and accelerator sources are examined. The results can become the basis for designing micromodels of blankets for subsequent verification benchmark experiments.



Coherent Bremsstrahlung on Colliding Beams and Possibility of its Detection
摘要
A new type of coherent electromagnetic process – coherent bremsstrahlung – on colliding beam setups with short bunches is examined. It is shown that solid-state photomultipliers can be used to detect, register, and investigate coherent bremsstrahlung.



Patient Radiation Dose During Radiological Examinations
摘要
This article contains information obtained in 2013 on the structure and number of radiological procedures by organ type and group and collective and average patient radiation dose on the territories within the jurisdiction of the Federal Medical-Biological Agency of Russia.



Testing Methods for Calculating Particle Coagulation and Settling in an Aerosol Module
摘要
Test results for models of particle coagulation and settling on a surface in an aerosol module in analytical tests and experiments are presented. A module is being developed for modeling the dynamics of polydisperse multicomponent aerosols in the first loop of VVER during a serious accident with emission of fission products from fuel elements into the coolant flow.


