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Том 123, № 2 (2017)

Article

Theoretical Prerequisites for PIK Reactor Subcriticality Control Aided by Spectral Noise Analysis

Degtyarev A., Ivanov A., Andryushchenko N., Myasnikov A., Zakharov A., Seryanina O., Sorokin S.

Аннотация

The possibility of measuring and controlling PIK reactor subcriticality on the basis of spectral analysis of reactor noise is examined. A simple lumped-parameter working model of the reactor and an equivalent noise source in accord with Schottky’s relation are used. Attention is focused on the statistical error of measurement of the spectral density of reactor noise owing to the finite measurement time and the random nature of neutron detection in a detector. It is shown that in connection with this error the measurements will require a long time and high-sensitivity detectors.

Atomic Energy. 2017;123(2):73-80
pages 73-80 views

Evaluation of the Radiological Consequences of Beyond Design Basis Accident for IRT MEPhI

Sakharov V., Shchurovskaya M., Alferov V., Geraskin N., Portnov A.

Аннотация

The results of an analysis of the radiological consequences of a beyond design basis accident for IRT MEPhI with high-enrichment uranium fuel and conversion to IRT-3M fuel assemblies with fuel kernel based the alloy U–9% Mo in an aluminum matrix with enrichment 19.7% are presented. The beyond design basis accident is assumed to be blocking of the flow section of the coolant in FA by a foreign object. It was postulated that a single eight-tube FA will melt in this accident. The analysis is performed using approximate conservative estimates. It is shown that the effective dose for the population does not exceed the admissible level. The radiological consequences of the accident for a reactor with high- and low-enrichment fuel are almost indistinguishable.

Atomic Energy. 2017;123(2):81-86
pages 81-86 views

CONV-3D Code Application for CFD-Modeling of Lead-Bismuth Coolant

Chudanov V., Aksenova A., Makarevich A., Pervichko V.

Аннотация

The results of testing the three-dimensional CFD-code on problems very close to real processes for lead–bismuth eutectic are presented: flow in a 19-fuel element assembly with three spacing lattices and convection in the ‘tumbler’ model. The results of convergence on a sequence of grids permit drawing the conclusion that for a 19-fuel element assembly the error in the calculation of the friction coefficient on a more finely divided grid does not exceed 10% with two-fold smaller grid step in each direction. Similar arguments are valid for the calculation of the hydraulic resistance coefficient.

Atomic Energy. 2017;123(2):87-92
pages 87-92 views

Operational Efficiency Evaluation of a Setup for Removing Stresses in the Steam Header of PGV-1000 Steam Generator

Adamenkov A., Malakhov I., Veselova I.

Аннотация

The effectiveness of a setup for removing stresses in the steam header of a PGV-1000 steam generator is evaluated. The evaluation is based on an investigation of the stress state by means of magnetic anisotropy measurements performed in the zone of the No. 111 weld seam of the hot header of steam generators operating in one of the power-generating units with a V-320 series reactor arrangement. Inspections made it possible to obtain cartograms of the distribution of the difference of the principal mechanical stresses along the perimeter of the weld connection of a PGV-1000 header equipped with a cooling mantle and headers without such a mantle. By means of statistical analysis of the data, a diagram of the distribution of the principal mechanical stresses was obtained. In addition, the distribution of the standard deviation of the principal mechanical stresses as a measure of the dispersion of a random quantity relative to its mathematical expectation was determined.

Atomic Energy. 2017;123(2):93-95
pages 93-95 views

Nuclear Fuel Based on Uranium-Zirconium Carbonitride

Chernikov A., Zaitsev V., Khromov Y.

Аннотация

The results of Investigations of the nitrogen and uranium pressure in the system U–Zr–C–N in the temperature range 1873–2073 K and the constructed section of the U–Zr–C–N phase diagram at 1873 K are presented. The behavior of the solid fission products in carbonitride fuel, the interaction of the fuel with a pyrolytic carbon coating, and the behavior of micro fuel elements based on such fuel during high temperature firing and in the presence of a temperature gradient are examined. The conditions for the preparation of fuel compositions of the type uranium carbonitride in a carbide-silicon matrix and some of its physicochemical and mechanical properties are determined. It is noted that there is promise in using fuel compositions and micro fuel elements based on uranium-zirconium carbonitride for high-temperature applications.

Atomic Energy. 2017;123(2):96-104
pages 96-104 views

Radwaste Self-Disposal in Geological Formations by Direct γ-Ray Heating of Rock

Arutyunyan R., Bol’shov L., Shvedov A.

Аннотация

The mechanism of direct heating of rock by radiation in order to transfer energy to the surrounding rock in penetration setups that use the heat released in radioactive decay is examined. The spatial distribution of the energy release owing to absorption of 60Co gamma rays in a layer of soil, salt, and ice is obtained. The temperature distribution and penetration rate are estimated for a 60Co based setup.

Atomic Energy. 2017;123(2):105-110
pages 105-110 views

Choice of Fine Packing for Rectification of Uranium Hexafluoride

Ezhov V.

Аннотация

Coefficients are proposed for the Bain–Hougen equation for calculating the limit velocity of vapor in a column filled with fine packing for the rectification of metal hexafluorides and their mixtures. It is shown that a simple method of comparing different packings in terms of the kinetic and hydrodynamic parameters is possible by using the effective throughput per unit volume of the packing, equivalent to one transfer unit.

Atomic Energy. 2017;123(2):111-116
pages 111-116 views

Monitoring the Presence and Location of Metallic Components Inside a Fuel Element

Ismagilov M., Skachkov E., Kadilin V., Fogel D.

Аннотация

A non-destructive method of monitoring the presence and location of metallic components in a fuel element is proposed. It is shown that a nickel plug can be identified by modernizing the measurement procedure. A method of performing measurements is described and the results of experimental studies are presented.

Atomic Energy. 2017;123(2):117-121
pages 117-121 views

Analysis of the Human Biohazard of Long-Lived Fission Products and Actinides for BREST-OD-300 Spent Fuel

Spiridonov S., Perevolotskii A., Perevolotskaya T., Aleksakhin R., Spirin E.

Аннотация

The aim of this work is to perform a comparative analysis of the biohazard for the population of long-lived fission products and actinides from BREST-OD-300 reactor spent fuel taking account of the time required for different radionuclides to reach Earth’s surface by migrating from a deep disposal site. It was found that the biohazard of fission products is significantly greater than that of actinides for a long time (20000 years according to the accepted scenario of radionuclide migration). The radiological impact on the population is predicted after 99Tc – radionuclide with high migration capability – reaches the soil surface. 137Cs and 90Sr will not appreciably affect the dose load because of their relatively short half-life. In order to maintain radio-ecological balance between long-lived wastes and native uranium during the entire possible time period, it is sufficient to extract from the BREST-OD-300 spent fuel 90% of the technetium and 75% of the americium with 99.9% of the fissile materials extracted.

Atomic Energy. 2017;123(2):122-126
pages 122-126 views

Modeling of Fission Product Transport in VVER Loop

Krapivin M., Laletin I., Moryakov A.

Аннотация

A method of calculating fission product transport in the first loop of VVER is proposed. In this method the coefficients of mass transfer are calculated using the CONTOUR hydraulic code. Computational results are reported for a problem where the transport of fission products in a reactor loop with partially damaged fuel elements is modeled.

Atomic Energy. 2017;123(2):127-134
pages 127-134 views

Evaluation of Radioactive Aerosol Precipitation on the Inner Surfaces of Steam-Water Lines in Beyond Design Basis Accidents at NPP with RBMK

Afremov D., Zhukov I., Pripachkin D., Budyka A.

Аннотация

The results of modeling performed with the MELCOR code of the transport and precipitation of fission product aerosols in the steam-water lines of RBMK during beyond design basis accidents are presented. It is shown that the precipitation of fission product aerosols on the inner surfaces of steam-water lines depends on the course of the accident and can be an effective mechanism for lowering their atmospheric emissions.

Atomic Energy. 2017;123(2):135-139
pages 135-139 views

Determination of the Most Likely Wear Zones of Pipe Bends in the Pulsed Pneumatic Conveyor at the RT-1 Plant

Istomin V., Voronin D., Khlebus K., Patoka D.

Аннотация

The results of an experimental investigation and numerical modeling of the most likely high-wear zones in 90° pipeline bends in the pulsed pneumatic conveyor system at the RT-1 plant of the Mayak Industrial Association are presented. The experimental studies were conducted on a model of a pulsed pneumatic conveyor system; the numerical modeling of the gas-dynamic flow in the pipeline channel was performed in a model of a two-dimensional non-stationary motion of a compressible medium. It was found on the basis of the experimental results obtained using the model and numerical modeling in the homogeneous approximation that local regions with high wear of walls in the 90° pipe bends in the pulsed pneumatic conveyor do indeed exist and their experimentally found positions agree with the calculations.

Atomic Energy. 2017;123(2):140-146
pages 140-146 views

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