Перегляд за темою "Thermal and fast reactor materials"

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Algorithm of technical diagnostics of the complicated damage to the continued resource of the circulation pipeline of the nuclear power plant

Hrinchenko, H.; Trisch, R.; Burdeina, V.; Chelysheva, S. (Вопросы атомной науки и техники, 2019)

The quality and safety of operation of the main circulating pipeline of the nuclear power plant is being studied in order to extend the life of the pipelines of the reactor unit of the NPP on the basis of the development ...
Analysis of reliability of the automatic core protection function of the reactor V-412 in response to local parameters: maximum linear power, departure from nucleate boiling ratio

Lys, S.S.; Semerak, M.M.; Kanyuka, A.I. (Вопросы атомной науки и техники, 2021)

The research subject is finding an engineering solution for V-412 core automatic protection during operation in both steady-state and transient conditions within ICIS using local parameters (i.e. maximum linear power, ...
A review: ferritic-martensitic steels – treatment, structure and mechanical properties

Rostova, H.Yu.; Tolstolutska, G.D. (Вопросы атомной науки и техники, 2022)

The constantly growing consumption of electricity requires the development and implementation of more powerful and energy-intensive systems of the new generation. Fusion and fission reactors of the 4th generation (Gen-IV) ...
A similarity criterion for spherical fuel elements free fall velocity in cylindrical channels with viscous liquid

Andrieieva, O.L.; Bulavin, L.A.; Tkachenko, V.I. (Вопросы атомной науки и техники, 2021)

The introduction of nuclear high-temperature gas-cooled reactors (HTGR) with an active zone based on spherical fuel elements (SFE) poses the task of determining the velocity of their free fall in cylindrical channels with ...
Assessment of the corrosion resistance of the main alternative materials for light water reactors tolerant fuel rod cladding

Zuyok, V.; Rud, R.; Tretyakov, M.; Rud, N.; Kushtym, Y.; Dykyy, I.; Shevchenko, I.; Rostova, H.; Shtefan, V. (Вопросы атомной науки и техники, 2022)

Basic materials for nuclear fuel rod claddings (Zr+1%Nb and E110 alloys), as well as alternative materials for tolerant fuel rod claddings (Cr18Ni10Тi steel and 42CrNiМo alloy), that are able to maximally prevent the ...
Burnup and radiation embrittlement of the U-Mo neutron source target

Borts, B.V.; Gann, V.V.; Zelinsky, A.Yu.; Parkhomenko, A.A.; Vanzha, A.F.; Marchenko, Yu.A.; Patochkin, I.V. (Вопросы атомной науки и техники, 2022)

The burnup of uranium target plates of the NSC KIPT neutron source was studied. An analysis of experimental work on the effect of neutron irradiation on the strength and plastic properties of uranium and U-Mo alloys under ...
CFD model as a digital twin of the radiation state of the new safe confinement of the chernobyl NPP

Krukovskyi, P.G.; Diadiushko, Ye.V.; Garin, V.O.; Tryfonov, O.V.; Kabanov, Yu.Yu. (Вопросы атомной науки и техники, 2020)

The necessity of a detailed analysis and prediction of the operating parameters and distribution of radioactive aerosols (RA) in the Shelter Object (SO), the New Safe Confinement (NSC) and the environment of the Chernobyl ...
Comparative characteristics of mechanical and adsorption properties of activated charcoals applied for adsorbers of NPP air discharge systems

Lepin, I.V.; Sibileva, R.M.; Sokolenko, V.I.; Vinokurov, E.I.; Grigorenko, M.A. (Вопросы атомной науки и техники, 2020)

This paper presents the results of studies on the strength and adsorption characteristics of granular activated charcoals of the brand ISQ DON GW4, С40/4 EXTRA KJ, and Norit RKJ4. The ultimate strength of samples was ...
Delving into some specific features of the magnetic systems used for the plasma recycling of the spent nuclear fuel (SNF)

Yuferov, V.B.; Katrechko, V.V.; Vinnikov, D.V.; Tkachev, V.I.; Sorokina, D.D. (Вопросы атомной науки и техники, 2022)

Consideration was given to some specific issues of the development of magnetic systems intended for the SNF plasma separators to separate, extract and deposit the actinides and also to magnetic systems of a different ...
Effect of hydrogenation on creep and structure evolution of nanocrystalline Zr1Nb alloy

Savchuk, E.S.; Sokolenko, V.I.; Karaseva, E.V.; Mats, A.V.; Frolov, V.A.; Pylypenko, M.M. (Problems of Atomic Science and Technology, 2023)

The regularities of creep, mechanical characteristics, and structure evolution of Zr1Nb nanocrystalline alloy obtained by intensive plastic deformation and hydrogenated from a gaseous medium are studied. It is shown that, ...
Effect of TiN inclusions and vibration loads on damage of heat exchange pipes of PGV-1000 steam generators

Mitrofanov, A.S. (Вопросы атомной науки и техники, 2022)

Operational damages of heat exchange tubes (HET) in steam generators of WWER-1000 power units were studied by means of metallography and scanning electron microscopy. The crack initiation and growth mechanism was found to ...
Efficiency of combined Fe and Pb radiation shield of transport casks for SNF transportation

Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V. (Вопросы атомной науки и техники, 2022)

The possibility of increasing the efficiency of combined iron and lead shielding of transport containers (TC) for SNF transportation by railroad is studied. Models for the transport of SNF γ-quanta are developed, that make ...
Electrode processes in electrolysis of zirconium at production of plastic zirconium for nuclear energy

Mukhachev, A.P.; Nefedov, V.G.; Kharytonova, O.A. (Вопросы атомной науки и техники, 2019)

The analysis of the conditions for industrial production of zirconium by the electrolysis of a melt of potassium fluorozirconate and potassium chloride in a sealed electrolyzer with a current load of 10 kA was carried out. ...
Empirical predicted residual life of the base metal of MCP of WWER-1000 reactors in operation

Gozhenko, S.V. (Problems of Atomic Science and Technology, 2023)

The comprehensive analysis of the results of research by direct methods of BM of MCP of the South-Ukraine NPP after 100,000 and 200,000 h of operation was carried out. In BM with a fine-grained initial structure, the first ...
Estimation of the dependence parameters of nuclear structural materials hardness on the content of gas impurities: an interval approach

Potanina, Т.V.; Yefimov, O.V.; Pylypenko, M.M. (Вопросы атомной науки и техники, 2021)

The applications of the interval and standard probabilistic approaches for verifying the reliability of the results of an experiment studying the mechanical properties of nuclear materials are compared. The presence of ...
Experimental study of transformation of carbonate system components cooling water of Rivne nuclear power plant during water treatment by liming

Kuznietsov, P.N.; Biedunkova, O.О.; Yaroshchuk, O.V. (Problems of Atomic Science and Technology, 2023)

The article presents research results on carbonate system components of cooling water, which has previously undergone water treatment by liming, depends on the cycle of concentration and absorption of carbon dioxide, which ...
Features of formation of crystallographic texture and properties in Ti-3Al-2.5V titanium alloy during tubes manufacture

Vakhrusheva, V.S.; Hruzin, N.V.; Malykhin, D.G. (Вопросы атомной науки и техники, 2019)

Texture formation processes at all technological stages of tube manufacture were considered. It has been established that at the stage of hot deformation and manufacture of TREX tubes, tangential and radial textures are ...
Forecasting of structural transformations in heat affected zone steel of 15Kh2NMFA at anti-corrosion cladding

Lobanov, L.M.; Kostin, V.А.; Makhnenko, O.V.; Zukov, V.V.; Kostenevich, E.S. (Вопросы атомной науки и техники, 2020)

Using mathematical modeling based on existing parametric regression equations the prediction of microstructure-phase transformations in heat affected zone( HAZ) metal of base material (steel 15Kh2NMFA) of WWER-1000 reactor ...
Formation of plastic properties of 12Cr18Ni10Ti steel highly irradiated by neutrons

Maksimkin, О.P.; Merezhko, D.А.; Merezhko, М.S.; Sarsenbayeva, K.B. (Вопросы атомной науки и техники, 2021)

New results of the experiments on the study of nature and patterns of the effect of anomalously high ductility of austenitic meta-stable irradiated steels are discussed, the possible causes of its formation and the ...
Fractal model of estimating quality of cold worked fuel cladding tubes

Vakhrusheva, V.S.; Volchuk, V.M.; Hruzin, N.V.; Tiutieriev, I.A. (Вопросы атомной науки и техники, 2021)

A possibility was considered concerning estimation of grain anisomery in the structure of fuel cladding tubes of corrosion-resistant 026Cr16Ni15Mo3Nb steel of austenitic class rolled according to two flow charts: regular ...

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Перегляд за темою "Thermal and fast reactor materials"

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