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Vol 126, No 4 (2019)

Article

On a Strategy for the Development of Nuclear Power in Russia

Alekseev P.N., Gagarinskii A.Y., Kalugin M.A., Kukharkin N.E., Semchenkov Y.M., Sidorenko V.A., Subbotin S.A., Teplov P.S., Fomichenko P.A., Asmolov V.G.

Abstract

The objectives of the development of reactor technologies for transitioning to two-component nuclear power with thermal and fast reactors as well as the issues arising in the analysis of development scenarios, including the uncertainty of the resource base and technical-economic performance, are discussed. It is shown that attempts to detail the structure of the nuclear power system in the second half of the 21st century do not yield unambiguous results, giving compelling reasons for strategic decisions. It is suggested that future work on strategic development be focused on the horizon periods of key decisions concerning the adoption of new reactor technologies.

Atomic Energy. 2019;126(4):207-212
pages 207-212 views

Basic Concepts of a Modular Fast Sodium Reactor with Metallic Fuel

Kotov Y.A., Alekseev P.N.

Abstract

The conceptual precepts of a modular fast sodium reactor with mixed uranium-plutonium zirconium-alloy metal fuel (U–Pu–Zr) related to Gen-IV are presented. The range of its parameters is determined, and the parameters are optimized in order to meet the characteristic requirements of the development of a nuclear power system in terms of safety, competitiveness, and resource availability. It was shown with the aid of computational studies that in a modular reactor, in spite of its small size, the systems requirements in terms of specific load and excess production are met and the minimum reactivity excess on burnup is realized. Loading metallic fuel into the core and thorium into the breeding zone and using fuel cycles compatible with thermal reactors it becomes much easier to solve the problems of supplying fuel for nuclear power and managing actinides and plutonium in the nuclear fuel cycle.

Atomic Energy. 2019;126(4):213-219
pages 213-219 views

Small Nuclear Power Plants – Primary Avenue for Reducing Risks and their Consequences in Nuclear Power

Alekseev P.N., Udyanskii Y.N., Shchepetina T.D.

Abstract

The potential for improving safety and systems efficiency via unit power reduction of NPP in spite of an increase of the specific costs is investigated. An approach to significant reduction of the risk due to the human factor by switching to small- and medium-size power-generating units is considered. This approach can becharacterized as a method of risk reduction by means of ‘power insurance.’ The qualitative technical and economic effects from the reduction of different forms of risk in the implementation of small- and mediumsize NPP designs as compared with large NPP are analyzed: public acceptance; search for investors and their financial risk; availability of NPP sites; cost increase due to longer construction times; radiation and nuclear safety risks; electric power interruptions; minimization of the reserve power in the power system; and, adaptability to the rate of regional energy growth. Variants of the classification of integral risks over the entire life cycle of an NPP design are presented.

Atomic Energy. 2019;126(4):220-225
pages 220-225 views

Distillation of Lithium Chloride From the Products of Uranium Dioxide Metalization

Salyulev A.B., Shishkin A.V., Shishkin V.Y., Zaikov Y.P.

Abstract

The possibility of purifying the metalized products of pyrochemical operations by removing the electrolyte by distilling off lithium chloride is checked experimentally. This study is performed in connection with the development of promising variants of an industrial method of metalizing uranium dioxide, which is the main component of the spent nuclear fuel after its voloxidation. The electrolyte was distilled from metalized pellets and powders based on uranium dioxide with their continuous evacuation at 700–900°C. It was found that the main component of the sublimates is lithium chloride; the content of rare-earth elements and uranium is very low. The distillation regimes where 98.8–99.9% of the LiCl can be removed from the metalized products were determined.

Atomic Energy. 2019;126(4):226-229
pages 226-229 views

Industrial Tests of the Modernized Separation Part of Moisture Separators-Reheaters at the Smolensk NPP

Egorov M.Y.

Abstract

The design of the modernized moisture separators-reheaters of the TG-1 and TG-2 turbines in the No. 1 unit of the Smolensk NPP is described. The modernization of intermediate moisture separators-reheaters eliminated the nonuniformity of the moisture distribution over the perimeter and height of the steam space behind the separation units. Tests showed that the average moisture content at the egress from the separation units was 0.6%, which is close to the computed value 0.5%.

Atomic Energy. 2019;126(4):230-234
pages 230-234 views

Sorption-Leaching Unification of Uranium Ore Pulp Processing

Molchanova T.V., Smirnov K.M., Krylova O.K.

Abstract

The results of studies of agitation leaching in combination with sorption leaching of uranium for different types of ores are reported. Sorption leaching reduces the consumption of sulfuric acid by 7–8% and reduces the processing time and makes it possible to obtain dump cakes with uranium content 0.005–0.007% and uranium concentration ≤5 mg/dm3 in the liquid phase of the discharge pulp, which corresponds to technological extraction of the uranium into anionite of at least 97%. The combined variant will make the fullest use of the capacity and potential of ion-exchange materials and permit unification of the enterprise’s process scheme.

Atomic Energy. 2019;126(4):235-241
pages 235-241 views

Corrosion Resistance of Experimental Fuel-Rod Cladding Tested in a Materials Science Research Reactor Under PWR Conditions

Izhutov A.L., Burukin A.V., Vladimirova O.N., Dolgov A.I., Il’in P.A., Kalygin V.V., Mokeichev M.A., Ovchinnikov V.A.

Abstract

Experimental fuel rods were tested in the PV-2 loop facility of the MIR reactor under conditions close to operation of full-size fuel rods in a PWR core. In the tests, the external condition of the cladding of the experimental fuel rods and structural elements of FA was evaluated visually; the thickness of the oxide film on the outer surface of the cladding of some fuel rods was measured. At the completion of the tests, all fuel rods remained tight, and no defects were found on the surface of the cladding and structural elements of FA. The thickness of the oxide film on the surface of the fuel rods made from the alloy E-110 (ultrapure), E-125 did not exceed 10 μm with average fuel burnup 32 MW·days/kg.

Atomic Energy. 2019;126(4):242-247
pages 242-247 views

Evaluation of the Technological Parameters of a Solution Target for 82Sr Production

Zagryadskii V.A., Latushkin S.T., Malamut T.Y., Novikov V.I., Ogloblin A.A., Unezhev V.N.

Abstract

The concept of a solution target for obtaining the radioisotope 82Sr via the reaction Rb(p, xn)82Sr is propounded. A computational estimate of the main technological parameters of a solution target is made. The 82Sr yield in a solution target is calculated for solutions of certain compounds of rubidium and initial proton energy 70 MeV. It is shown that the highest 82Sr yield 7.44 MBq/(μA·h) in a solution target can be obtained by using a saturated solution of RbF. The solution fl ow rate in the circulation loop of the target allowing the operation of a target without boiling-up in a 100 μA proton beam is obtained for a target solution with RbF. The mass/size parameters of the heat-exchanger allowing the solution to be cooled tothe initial temperature in a single pass are calculated. The infl uence of radiolysis of the proton-irradiatedsolution on the operation of the target is determined. It is shown that on the whole radiolysis of the solution target is not large but does require defi nite efforts to utilize the hydrogen.

Atomic Energy. 2019;126(4):248-253
pages 248-253 views

Accuracy Enhancement of γ-Albedo Geological Core Analysis

Pak Y.N., Balbekova B.K., Pak D.Y., Kenetaeva A.A., Syzdykov N.E.

Abstract

A method of improving the accuracy of geological core analysis performed by the γ-albedo method is examined. The regularities of the rotation of a cylindrical core around its axis and the reciprocating motion of the probe along the core, parallel to its surface, such that the γ-radiation scattered from each individual surface makes the same contribution are determined. The effectiveness of the proposed method is confirmed by the possibility of minimizing the analytical error arising due to the non-uniformity of the material.

Atomic Energy. 2019;126(4):254-258
pages 254-258 views

Volume-Localized Quantum Levels in Charged Fullerenes

Arutyunyan R.V., Osadchii A.V.

Abstract

The existence of a system of short-lived, discrete, volume-localized, electronic, quantum levels in positively charged fullerenes is shown theoretically and numerically for the example of the fullerenes C60. The results of three-dimensional calculations performed using the QuantumEspresso package are presented. The structures of the quantum levels in charged fullerenes were calculated numerically in a wide range of transitions from 4 eV for the fullerene \( {C}_{60}^{+ 1} \) to 40 eV for the fullerene \( {C}_{60}^{+ 1} \). The results confirm previous theoretical work on the possible existence of single-particle excited electronic states localized in the volume of positively charged fullerene C60. Thus, the electrons captured in these discrete levels of fullerene form a kind of short-lived superheavy pseudoatom in which the electrons are localized inside a positively charged spherical nucleus with atomic mass 240 a.u. for C20 and 720 a.u. for C60. In conclusion, the possibility of generating coherent radiation on these transitions is discussed.

Atomic Energy. 2019;126(4):259-263
pages 259-263 views

Radioactivity Monitoring of the Surface Air Layer and Atmospheric Fallout Near NPP

Kryshev I.I., Bulgakov V.G., Kryshev A.I., Katkova M.N., Sazykina T.G., Pavlova N.N., Kosykh I.V., Gnilomedov V.D., Buryakova A.A., Gaziev I.Y.

Abstract

The emissions from Russian NPP in 2011–2017, which, on the whole, taking the specifics of nuclear reactors into consideration, correspond to the global emissions, are analyzed. The public irradiation dose due to NPP emissions is estimated to be 0.01–0.1% of the dose due to natural background radiation. It is shown that the location of fixed stations for monitoring the radioactivity of the surface air layer and atmospheric fallout near NPP meets the requirements of Russian regulatory documents and IAEA recommendations. The volume activity of 137Cs, 60Co, and other technogenic radionuclides in the surface air layer in the NPP observation zones are 104–108 times lower than the volumetric activity admissible for the public. To improve the monitoring of the radiation conditions, the 14C and 3H present in the emissions from NPP must be monitored, and collection of atmospheric fallout at fixed observation stations near NPP must be more efficient.

Atomic Energy. 2019;126(4):264-271
pages 264-271 views