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Vol 122, No 2 (2017)

Articles

IBR-2M Reactor Power Feedback Parameters Evaluation Using Square Reactivity Oscillations

Pepelyshev Y.N., Popov A.K., Sumkhuu D.

Abstract

The parameters of a mathematical model of power feedback are evaluated on the basis of an analysis of transient power processes arising in the IBR-2M reactor as a result of intentional square oscillations of the reactivity during operation in a self-regulation regime. The power feedback is described by three linear difference equations and represented in the form of three aperiodic elements connected in parallel. Two components play the role of negative and one component positive feedback. The total feedback is negative, i.e., it has a stabilizing effect on the operation of the reactor. The slowest negative component of power feedback is probably due to axial swelling of the fuel as it heats up. Since the power feedback parameters change in the course of operation, their periodically repeated evaluations are one way of securing the operational safety and reliability of the reactor.

Atomic Energy. 2017;122(2):75-80
pages 75-80 views

Article

Comparative Geological and Mineral-Petrological Analysis of Ore-Bearing Rock in Lithium and Beryllium Deposits for Modeling the Behavior of Ore Minerals During Processing

Kol’tsov V.Y., Yudina T.B., Azarova Y.V., Semenov A.A., Lizunov A.V., Lesina I.G.

Abstract

A comparative analysis of ore-bearing rock in the Zavitinskoe and Ermakovskoe deposits is made. Such an analysis is needed because of the requirements of working with ore-mining concentrates, which model the basic physical and chemical parameters of beryllium-containing concentrates that influence their preparation efficiency and subsequent opening with reagents. It was found that it is possible to develop a general model system for the chemical and physical behavior of lithium and beryllium ore minerals and the bearing rock in the Ermakovskoe and Zavitinskoe deposits. Ore materials in the Zavitinskoe deposit (lithium association) model the physicochemical behavior of beryllium-containing ore minerals in the Ermakovskoe deposit (beryllium association).

Atomic Energy. 2017;122(2):81-86
pages 81-86 views

Analysis of the Effect of the Stress-Strain State of Irradiated Zirconium-Alloy Fuel-Element Cladding on Hydride Orientation

Kulakov G.V., Vatulin A.V., Konovalov Y.V., Kosaurov A.A., Peregud M.M., Korotchenko E.A., Shishin V.Y., Shel’dyakov A.A.

Abstract

The effect of the stress distribution on the hydride distribution in zirconium cladding of fuel elements with dispersion fuel is analyzed. It is shown that reorientation of zirconium hydrides can occur in fuel-element cladding under the action of tensile stresses, which can result in the appearance of radially oriented hydrides and plasticity reduction in the cladding upon cool-down of the fuel elements. The threshold tensile stresses are determined in the cladding in the unirradiated and irradiated states, in which hydride reorientation from tangential to radial occurs.

Atomic Energy. 2017;122(2):87-92
pages 87-92 views

Effect of Damaging Irradiation on Low-Temperature Embrittlement of Metals

Chernov V.M., Moroz K.A.

Abstract

The effect of low-temperature damaging irradiation on the high-temperature embrittlement (cold shortness) in metals was investigated in a previously proposed model. The cold shortness state with possible brittle fracture in metals is not formed in the irradiation process because of the dynamical radiation processes arising.

Atomic Energy. 2017;122(2):93-98
pages 93-98 views

Membrane Electrolysis in Beryllium Hydroxide Production Technology

Nikolaevskii V.B., Kotsar’ M.L., Matyasova V.E.

Abstract

Experimental studies of the electrochemical neutralization of an alkaline solution for the production of beryllium hydroxide with simultaneous regeneration of NaOH are expounded. The kinetics is studied and the basic technological parameters are determined – current density, voltage, duration, and specific electricity consumption. The use of MF-4SK instead of MK-40 membranes in the neutralization of alkali in two stages approximately halves the process time. The concentration of the regenerated solution reaches 450 g/dm3, as required for autoclave opening. It is shown that in principle membrane electrolysis can be used for neutralization and parallel regeneration of alkali in reprocessing solutions after autoclave opening of raw material. A technological scheme is proposed for obtaining beryllium hydroxide by membrane electrolysis.

Atomic Energy. 2017;122(2):99-105
pages 99-105 views

Vizart Software for Balance Calculations of Material Flows in Closed Nuclear Fuel Cycle Technologies

Shmidt O.V., Tret’yakova S.G., Evsyukova Y.A., Makeeva I.R., Dubosarskii V.G., Pugachev V.Y., Rykunova A.A.

Abstract

The VIZART software for computer modeling of production operations in the reprocessing of spent nuclear fuel, fabrication of nuclear fuel, and management of radioactive wastes was developed as part of the work on the complex technology of closed NFC. It makes it possible to develop models of process schemes or individual operations and perform supporting balance calculations of material flows of the prescribed schemes. A functional for calculating the material balance of products in a scheme taking account of the equipment productivity and constructing sequence diagrams of equipment operation was developed. The presented software, unlike most general-chemical simulators, makes it possible to calculate the characteristics of products which are specific for radiochemical processes: the isotopic composition and its variation during reprocessing, radioactivity, and heat release. These characteristics are important for validating the design and structural solutions from the standpoint of nuclear and fire-explosion safety.

Atomic Energy. 2017;122(2):106-111
pages 106-111 views

Immobilization of Highly Toxic Beryllium-Containing Wastes in Cement Compound Using Polycarboxylate Super-Plasticizers

Semenov A.A., Shipunov N.I., Zhidelev A.I., Korobeinikov D.A., Lesina I.G., Denisov A.S., Zabirova N.E., Saifutdinova S.E., Lizunov A.V., Kupriyanov I.B., Saikin S.P., Filimonova N.V.

Abstract

A technology has been developed for immobilizing highly toxic beryllium-containing wastes in a cement compound using polycarboxylate superplasticizers. Two cement mixture compositions, containing polymer superplasticizer comprised of polycarboxylate with high strength in compression, high frost resistance, water impermeability, and resistance to beryllium leaching were developed. The proposed compositions guarantee confi nement of beryllium for a long period of time.

Atomic Energy. 2017;122(2):112-117
pages 112-117 views

FAN15 Code Modeling of Electron and Positron Transport

Savitskaya E.N., Sannikov A.V.

Abstract

A method of modeling the transport of electrons and positrons with energies 1 keV–10 MeV implemented in the FAN15 code is described. The code takes account of multiple Coulomb scattering, fl uctuations of ionization losses, formation of δ-electrons, and Bremsstrahlung and x-ray photons. The EEDL and EADL evaluated data libraries are used in the calculations of Bremsstrahlung and emission of x-ray photons upon relaxation of ionized atoms. The computational results are compared with the experimental data on the energy, angular, and dose distributions of 0.5–10 MeV electrons in different absorbers.

Atomic Energy. 2017;122(2):118-124
pages 118-124 views

Microdosimetric Interpretation of the Dose and Dose Rate Efficiency Coefficient

Sakovich V.A.

Abstract

A model of a hypothetical process resulting in damage to DNA by ionizing radiation, as a result of which a nonlinear dose dependence of carcinogensis can form at dose 10–100 mGy, is examined on the basis of a microdosimetric approach. The model assumes that the primary damage to DNA interacts with short-lived products of irradiation before the DNA is repaired or transformed into a precancerous defect that is transferred to a daughter cell. It is shown that there are grounds for using the ICRP effective dose and dose rate lowering coefficient equal to 2 in the evaluation of the lifetime risk of irradiation with a significant dose and in the validation of criteria for radiation safety on the basis of data on morbidity and mortality in a cohort of Japanese atomic bomb survivors.

Atomic Energy. 2017;122(2):125-130
pages 125-130 views

Infrastructure Objects of the Nuclear Fleet as Sources of Radioactive Contamination of the Barents Sea: Waste Repository in Guba Andreeva

Il’in G.V., Kasatkina N.E., Moiseev D.V., Usyagina I.S.

Abstract

The impact of temporary storage sites for radioactive wastes in Guba Andreeva on the environmental conditions in the coastal zone of the Barents Sea after 50 years of operation is evaluated on the basis of general chronological reconstruction of the dynamics of radioactive contamination of the marine environment. The bottom deposits along the seacoast at different distances from the repository were investigated. It was found that the region of constant impact of the repository on the conditions in the marine environment is localized near the perimeter of the sanitary-protective zone. Growth of the specific activity of 137Cs, 90Sr, 238Pu, 239,240Pu is recorded in sediments layers up to the level 16–20 cm. The impact of the emission of radionuclides from the repository site is not perceptible in the seacoast zone (Motovskii Zaliv). The age of the sedimentary layers was determined: it shows that the significant concentration of 137Cs in the deposits in Motovskii Zaliv corresponds to the mid-1960s and 1986 and is associated with atmospheric fallout of radionuclides as a result of the nuclear weapons tests and the accident at the Chernobyl NPP.

Atomic Energy. 2017;122(2):131-137
pages 131-137 views

Analytical Reviews

Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016)

Dragunov Y.G., Gabaraev B.A., Dzhalavyan A.V., Lopatkin A.V., Pimenov A.O., Strebkov Y.S., Lemekhov V.V., Moiseev A.V., Cherepnin Y.S., Arkhipov O.P., Evropin S.V., Ryasnyanskii S.G., Kulikov D.G., Afremov D.A., Danilov I.V.
Atomic Energy. 2017;122(2):138-142
pages 138-142 views