Atomic Energy

Atomic Energy is a peer-reviewed journal focusing on the peaceful uses of atomic energy.

  • Covers a broad range of topics including nuclear chemistry and physics, plasma physics, and accelerator characteristics.
  • Delivers insights into reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
  • Translated from the Russian journal, Atomnaya Energiya.
  • Special attention is given to all aspects of the nuclear fuel cycle.

Current Issue

Open Access Open Access  Restricted Access Access granted  Restricted Access Subscription Access

Vol 126, No 6 (2019)

Article

Investigation of Spatial Effects Accompanying Local Boiling of Coolant in VVER Core on the Basis of Neutron Flux Noise Analysis
Shumskii B.E., Vorob’eva D.V., Mil’to V.A., Semchenkov Y.M.
Abstract

Situations with local boiling of the coolant become more likely when VVER-type power units are transferred to a heightened power level. In a VVER core, neutron flux detectors are not present in all FA. An important problem for evaluating the possibility of detecting local boiling in FA which are not equipped with detectors is the study of the spatial distribution of the change brought about in the neutron flux noise by local boiling of the coolant. The results of an investigation of the spatial distribution of the neutron flux noise initiated by fluctuations of the coolant parameters at the ingress into the core with non-equilibrium local surface boiling are reported. The sensitivity of the neutron flux noise in FA with no boiling to local boiling in neighboring FA is analyzed. The results could be helpful in analyzing the data recorded by the in-reactor noise diagnostics system in commercial operation in operating power-generating units.

Atomic Energy. 2019;126(6):345-350
pages 345-350 views
Radiative Heat Exchange in a Gas Cavity Above Reactor Core Melt During a Serious Accident
Kamenskaya D.D., Filippov A.S.
Abstract

A model of radiative heat-exchange, based on the Rosseland approximation, in a gas cavity was introduced into the HEFEST computational code designed for modeling the interaction of the core melt with NPP structures during a serious accident in VVER. This approach is admissible for optically dense gas and supplements the zonal heat exchange model, already existing in the code, for a cavity with a transparent gas. The conditions for using these two approaches in modeling radiative heat transfer at different stages of an accident are discussed. The numerical implementation of the diffusion model and its verification are described. The model was tested on the problem of radiative heat exchange during melt retention at the bottom of the vessel of a VVER-1000 reactor and the results are reported.

Atomic Energy. 2019;126(6):356-362
pages 356-362 views
Influence of Rheological Characteristics of Concrete on the Stress-Strain State of NPP Containment
Medvedev V.N., Skorikova M.I.
Abstract

A comparative analysis is presented of the influence of the rheological characteristics of concrete on the stress strain state of NPP containment shells. It is based on creep and shrinkage tests performed on concrete, field observations, and calculations of the strains and stresses engendered in the reinforcement and concrete by the shrinkage and creep of concrete. The results showed discrepancies in the obtained data. For this reason, it is recommended that field data and detailed working models, in which the cross-section parameter and the pitch of the reinforcement rods correspond to the nominal values, be used in evaluating the stress-strain state of NPP containment under operational and accidental loads.

Atomic Energy. 2019;126(6):363-367
pages 363-367 views
Investigation of PuF3 and AmF3 Solubility in 73LiF–27BeF2 Melt
Lizin A.A., Tomilin S.V., Osipenko A.G., Nezgovorov N.Y., Ignat’ev V.V., Kormilitsyn M.V.
Abstract

Using an experimental stand for studying the solubility of fluorides, measurements were performed at 550–700°C with step 50°C and the solubility of plutonium and americium trifluorides in melt with molar composition 73LiF–27BeF2 was calculated. Previously, such measurements were not performed for plutonium and americium trifluoride. The temperature dependence of the solubility of plutonium and americium trifluoride for the given salt system was constructed. The obtained solubility for plutonium trifluoride is appreciably higher than in a similar salt system with a higher content of beryllium difluoride. The obtained data on the solubility of americium and plutonium trifluoride can be used to select the minimum temperature of the fuel salt of a molten-salt reactor.

Atomic Energy. 2019;126(6):368-371
pages 368-371 views
Mathematical Model of Cadmium Distillation at the Stage of Pyrochemical Reprocessing of Spent Mixed Uranium-Plutonium Nitride Nuclear Fuel
Egorova O.V., Liventsova N.V., Liventsov S.N., Shmidt O.V.
Abstract

A mathematical model of the technological process of cadmium distillation at the stage of pyrochemical reprocessing of spent mixed uranium-plutonium nitride fuel for the purpose of studying the serviceability of and developing monitoring and process control systems is presented. The basic thermodynamic and kinetic characteristics and the principles of mathematical modeling of vacuum distillation of liquid mixtures, specifically, cadmium, are described. The requirements of the model and the assumptions are formulated. The information structure and mathematical description of the model were developed. Computational experiments were performed on the model and showed its serviceability and possibility of use for developing monitoring and process control systems.

Atomic Energy. 2019;126(6):372-378
pages 372-378 views
Rotor Length Dependence of the Separative Power of a Gas Centrifuge
Aleksandrov O.E.
Abstract

An analytical expression is obtained for the dependence of the maximum separative power of a centrifuge on the rotor length taking the feed flow into account. It is shown that the maximum separative power of a centrifuge is a nonlinear function of the rotor length.

Atomic Energy. 2019;126(6):379-382
pages 379-382 views
Investigation of the Influence of the Magnetic Field of a Well on the Neutron Tube of a Geophysical Apparatus
Rachkov R.S., Presnyakov A.Y., Yurkov D.I.
Abstract

The results of experimental studies of the effect of the magnetic field of the well casing on the operation of the gas-filled neutron tube used in the logging equipment are reported. The operation of the ion source was evaluated in terms of the parameters of the pulsed currents of charged particles recorded at the target of the neutron tube. Analysis shows that a longitudinal magnetic field, as compared with a transverse magnetic field, has a greater influence on the performance of the tube. Of the screening methods studied the one with a robust magnetic-steel housing for the equipment turned out to be most effective.

Atomic Energy. 2019;126(6):383-387
pages 383-387 views
Verification of a Mathematical Model for Calculating the Effective Irradiation Dose Rate from Contaminated Soil and Building Walls Taking Screening into Account
Dzama D.V., Sorokovikova O.S.
Abstract

A three-dimensional code for calculating the propagation of radioactive contamination under conditions of industrial development in the presence of atmospheric emissions is being developed at IBRAE RAS. The effective irradiation dose rate from a cloud, contaminated soil, and building walls is calculated on the basis of modeling. The screening of ionizing radiation by building walls is taken into account. The present work is devoted to verifying a method of calculating the effective irradiation dose rate due to contaminated soil and building walls. Two test problems are examined: with the contaminated surface of a cone-shaped building and a section of soil. It is concluded on the basis of the solution of problems that the accuracy of the method used in the three-dimensional computational code is acceptable.

Atomic Energy. 2019;126(6):388-392
pages 388-392 views
Recovery of the Surface Density of Radionuclide Contamination of Soil from Aerogamma Survey Data
Aron D.V., Gavrilov S.L., Kiselev A.A., Shvedov A.M.
Abstract

The recovery of non-uniform surface contamination density from measurements of instrumental spectra performed by the airborne survey method is examined. An algorithm based on Tikhonov’s method of regularization is proposed for solving the inverse problem. The results of testing the chosen algorithm on model problems of recovering the 137Cs contamination of a soil surface in the form of spots with different activity and size are presented. The influence of the regularization parameter on the recovery error is analyzed, and the optimal values of the regularization parameter are obtained.

Atomic Energy. 2019;126(6):393-398
pages 393-398 views
Angular Distribution of 8.5 MeV Electron Bremsstrahlung
Ryvkin B.N., Skachkov E.V.
Atomic Energy. 2019;126(6):404-406
pages 404-406 views
Computational Modeling of Systems with Low Heat Fluxes
Osipov A.M., Gol’tsev A.O., Il’in A.V., Fedosov A.M., Zakharova L.N.
Abstract

The results of computational modeling of experiments with heating of a water-filled and dewatered system are reported. The aim of the experiments was to test the computational methods used to analyze accidents in RBMK spent fuel storage, which is an example of a system with low heat fluxes. The calculations were performed using the RELAP5 code and a model specially developed for analyzing such experiments. It is shown that the RELAP5 code with the Reflood option gives acceptable results, but for lack of a description of surface evaporation in the code water level reduction in the calculations starts with a delay (after water boils) and occurs faster than in the experiment. When surface evaporation is taken into account by means of Balter’s empirical relation, the time dependence of the water level coincides with the experimental dependence. The variation of temperature at the control points of the heater is also close to the experiment. The heating of a dewatered system is described well by both models. Heat transfer by radiation from the heater to the vessel walls and into the ambient environment plays the main role.

Atomic Energy. 2019;126(6):351-355
pages 351-355 views

Scientific and Technical Communications

Mathematical Model of Pump Electric drive for Integral Models of NPP Power-Generating Units
Polyakov A.M., Subbotin P.V., Fedorovskii A.Y., Khodakovskii V.V.
Atomic Energy. 2019;126(6):399-403
pages 399-403 views

This website uses cookies

You consent to our cookies if you continue to use our website.

About Cookies