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| Issue | Title | |
| No 1 (2020) | RESEARCH OF SOME THERMOPHYSICAL FEATURES OF THE PROCESS OF PROTECTIVE PYROCARBON COATING APPLICATION ON A COATED PARTICLE FUEL MODEL | Abstract PDF (Rus) similar documents |
| K. Simeyko | ||
| "... , samples of models of coated particle fuel coated with pyrocarbon were obtained. ..." | ||
| No 3 (2019) | DEVELOPMENT OF SOME ACCOMPANYING TECHNOLOGIES OF IV GENERATION NUCLEAR REACTORS WITH COOLANT GAS | Abstract PDF (Rus) similar documents |
| К. V. Simeiko | ||
| "... -grade graphite, pyrocarbon protective coatings of nuclear microfuel, production of helium. The Gas ..." | ||
| No 1 (2019) | DEVELOPMENT OF TECHNOLOGY TO STUDY PROPERTIES OF IRRADIATED FUEL OF HIGH-TEMPERATURE GAS-COOLED REACTOR | Abstract PDF (Rus) similar documents |
| Sh. Kh. Gizatulin, D. S. Dyussambayev, A. A. Shaimerdenov, P. P. Silnyagin, N. Burtevayev, Sh. Ueta | ||
| "... -structured isotropic fuel with an outer diameter of 0.92 mm. Particles have a triple coating of pyrocarbon ..." | ||
| No 3 (2018) | THERMOPHYSICAL ANALYSIS OF PROCESS OF URANIUM CARBIDE OBTAINING APPLYING ELECTROTHERMAL FLUIDIZED BED TECHNOLOGY | Abstract PDF (Rus) similar documents |
| K. V. Simeiko | ||
| "... Uranium carbide is one of advanced types of nuclear reactor fuels. Existing technologies ..." | ||
| No 1 (2019) | DEVELOPMENT OF TECHNOLOGY OF ELECTROCHEMICAL SEPARATION OF FUEL ELEMENT OF HTGR | Abstract PDF (Rus) similar documents |
| D. S. Dyussambayev, Sh. Kh. Gizatulin, A. A. Shaimerdenov, P. P. Silnyagin, A. M. Akhanov, N. Burtevayev, Sh. Ueta | ||
| "... fuel is a spherical microfuel, which are compressed into a graphite compact, from which fuel assemblies ..." | ||
| No 2 (2021) | DEVELOPMENT OF TECHNOLOGIES OF SILICON CARBIDE PRODUCING (REVIEW) | Abstract PDF (Rus) similar documents |
| K. V. Simeiko, A. I. Malinouski,, A. Zh. Grebenkov, S. Yu. Sayenko, K. V. Lobach, A. D. Kustovska, O. O. Liaposhchenko, V. I. Sklabinskyi | ||
| "... silicon carbide is the carbothermal reduction of silica encapsulated with pyrocarbon in reactors ..." | ||
| No 2 (2025) | RADIATION AND NUCLEAR SAFETY ANALYSIS FOR THE SPENT FUEL TRANSPORTATION PACKAGE AFTER THE SHORT-TERM COOLING BY USING COMPUTER SIMULATION MODELING METHODS | Abstract PDF (Eng) similar documents |
| D. B. Zarva, Ye. S. Tur, S. A. Mukeneva, A. V. Gulkin, E. G. Batyrbekov, V. A. Vityuk | ||
| "... container for the spent nuclear fuel after short-term cooling. Calculations for radiation protection have ..." | ||
| No 4 (2024) | STUDY OF POROUS SILICON AS A FUEL CELL MEMBRANE | Abstract similar documents |
| М. К. Skakov, А. М. Zhilkashinova, А. Zh. Miniyazov, N. Kantay, А. Kydyrmolla, S. Kabdrakhmanova, N. М. Mukhamedova, G. К. Zhanbolatova | ||
| No 1 (2023) | CALCULATED AND EXPERIMENTAL DATA ON ENERGY RELEASE PROFILE IN THE FUEL ASSEMBLY OF THE IVG.1M REACTOR AFTER FUEL ENRICHMENT REDUCTION | Abstract PDF (Rus) similar documents |
| R. R. Sabitova, Yu. A. Popov, R. A. Irkimbekov, I. V. Prozorova, S. V. Bedenko | ||
| "... Prior to the commissioning of the IVG.1M reactor with low-enriched uranium fuel, experimental ..." | ||
| No 4 (2025) | CALCULATION OF RADIONUCLIDE ACCUMULATION IN A VVER-1000 FUEL ASSEMBLY AFTER THE FIRST FUEL CYCLE | Abstract similar documents |
| D. M. Seken, A. S. Surayev, N. E. Mukhamedov, R. A. Irkimbekov, O. M. Zhanbolatov | ||
| "... after the first fuel cycle using the MCNP6 code and the ENDF/B-VII nuclear data libraries. Calculations ..." | ||
| No 4 (2018) | CONVERTER OF IGR NEUTRONS FOR TESTING OF FAST REACTORS FUEL ELEMENTS | Abstract PDF (Rus) similar documents |
| V. M. Kotov, O. M. Zhanbolatov | ||
| "... . For these purposes it is necessary to carry out experiments with fuels of fast reactors. However, in a thermal ..." | ||
| No 4 (2018) | EXPERIMENTAL STUDIES FOR THE HIGH-TEMPERATURE OXIDATION OF THE HTGR FUEL PROTOTYPE | Abstract PDF (Rus) similar documents |
| S. K. Askerbekov, Ye. V. Chikhray, T. V. Kulsartov, V. P. Shestakov, Zh. A. Zaurbekova, I. E. Kenzhina, Yu. N. Gordienko, Yu. V. Ponkratov | ||
| "... of a prototype HTGR fuel in an oxygen environment under the following experimental conditions: the maximum ..." | ||
| No 4 (2019) | CONDITION OF THE MATERIAL OF THE CASE OF EXHAUST BN-350 REACTOR FUELS IN LONG STORAGE | Abstract PDF (Rus) similar documents |
| Ye. A. Kozhakhmetov, Ye. T. Koyanbaev, Ye. D. Dauletkhanov, R. M. Mukhamedzhanova, A. S. Urkunbay, Ye. Ye. Sapatayev | ||
| "... of the deflection of the cover fragments as a result of radiation swelling and creep of fuel assemblies ..." | ||
| No 3 (2019) | INFLUENCE OF THE THERMACYCLING PROCESS ON THE STRENGTH PROPERTIES OF THE LEU AND HEU FUEL OF IGR REACTOR | Abstract PDF (Rus) similar documents |
| Ye. D. Dauletkhanov, Ye. Ye. Sapataev, Ye. A. Kozhakhmetov, R. M. Mukhamedzhanova, A. Zh. Beldeubaev, A. S. Urkunbay | ||
| "... enriched uranium (LEU) fuel materials of the IGR reactor after thermal cycling at different temperatures ..." | ||
| No 3 (2021) | APPLICATION OF THE VOLUME OF FLUID METHOD TO SIMULATE THE PROCESS OF MELTING AND MOVEMENT OF FUEL | Abstract PDF (Rus) similar documents |
| Y. A. Kabdylkakov, A. S. Suraev | ||
| No 3 (2021) | EXPERIMENTAL STUDIES ON DEVELOPMENT OF THE METHOD FOR DETERMINING THE AMOUNT OF IMPURITATED GASES IN NUCLEAR FUEL | Abstract PDF (Rus) similar documents |
| G. A. Vityuk, V. A. Vityuk, A. D. Vurim, R. Y. Kelcingazina, B. Y. Bekmagambetova | ||
| "... The article is devoted to an issue of estimating the impurity gas amount in nuclear fuel ..." | ||
| No 1 (2020) | SUBSTANTIATION OF AN EXPERIMENTAL STUDY TECHNOLOGY OF FUEL RODS OF FAST REACTORS IN THE IGR | Abstract PDF (Rus) similar documents |
| V. М. Kotov, О. M. Zhanbolatov, N. A. Suleymenov | ||
| "... The paper addresses issues of providing the representative experiments with fuel rods of fast ..." | ||
| No 3 (2020) | SAFETY CULTURE IN TECHNOLOGIES FOR HANDLING NUCLEAR WASTE AND NUCLEAR FUEL | Abstract PDF (Rus) similar documents |
| N. V. Gorin, V. S. Krayev, V. G. Smirnov, A. P. Vasilyev, A. N. Andreyuk, S. V. Burenkov, V. M. Kutsenko | ||
| "... and spent nuclear fuel. These technologies have been implemented by RFNC-VNIITF together with RFNC-VNIIEF ..." | ||
| No 4 (2024) | METHODOLOGY OF SELECTING CEMENT MATRIX COMPOSITION FOR IMMOBILIZATION OF IRRADIATED URANIUM-GRAPHITE FUEL | Abstract PDF (Rus) similar documents |
| O. S. Bukina, Yu. Yu. Baklanova, M. N. Azbergenov, M. А. Kuksa | ||
| "... of the research reactor is a stack of uranium-graphite blocks (fuel elements) enriched to 90 wt. % in 235U isotope ..." | ||
| No 2 (2025) | IMPROVEMENT OF METHODS FOR MODELING THE MELTING OF FUEL ASSEMBLIES IN THE CONDITIONS OF AN EXPERIMENT ON IGR RECTOR | Abstract PDF (Rus) similar documents |
| E. A. Kabdylkakov, A. S. Suraev, O. M. Zhanbolatov, G. A. Vityuk, R. A. Irkimbekov | ||
| "... Experimental studies of the process of fuel destruction at the IGRY reactor make it possible ..." | ||
| No 1 (2025) | DEVELOPMENT AND CREATION OF RESEARCH CELLS FOR SOLID OXIDE FUEL CELLS | Abstract PDF (Eng) similar documents |
| S. Opakhai, K. A. Kuterbekov, K. Zh. Bekmyrza, A. M. Kabyshev, M. M. Kubenova, N. K. Aidarbekov, Zh. Zhumadilova | ||
| "... The article is devoted to the development and creation of research cells for solid oxide fuel ..." | ||
| No 3 (2022) | ANALYSIS OF THERMAL STATE OF A WCTC-LEU FUEL ELEMENT OF THE IVG.1M REACTOR WHEN FUEL KERNEL SEPARATING FROM THE CLADDING | Abstract PDF (Rus) similar documents |
| S. M. Khasenova, O. A. Stepanova, A. S. Akaev, Ye. A. Martynenko, A. S. Suraev | ||
| "... This article presents an analysis of thermal state of a fuel element of the WCTC-LEU of the IVG.1M ..." | ||
| No 2 (2023) | ON THE ISSUE OF EFFICIENT COMBUSTION OF NON-DESIGN COAL KARAZHYRA | Abstract PDF (Rus) similar documents |
| A. R. Khazhidinova, О. A. Stepanova, М. V. Yermolenko, A. S. Khazhidinov | ||
| "... unit are the qualitative composition of the fuel being burned, the behavior of the mineral part ..." | ||
| No 3 (2022) | IMPLEMENTATION OF IAEA SAFEGUARDS IN A STATE WITH AN IMPORTED FAST REACTOR AND A CLOSED NUCLEAR FUEL CYCLE | Abstract PDF (Rus) similar documents |
| N. V. Gorin, E. V. Kuznetsov, N. P. Voloshin, V. P. Kuchinov, A. N. Chebeskov, A. P. Vasilyev, A. V. Moiseev, V. V. Shidlovsky | ||
| "... -Proliferation Treaty) that has imported the fast-neutron reactor with nuclear fuel cycle facilities ..." | ||
| No 4 (2018) | COMPARISON OF NEUTRON SPECTRUM IN THE WWR-K REACTOR WITH LEU FUEL AGAINST HEU ONE | Abstract PDF (Rus) similar documents |
| S. N. Koltochnik, D. S. Sairanbayev, L. V. Chekushina, Sh. Kh. Gizatulin, A. A. Shaimerdenov | ||
| "... in 1967 with enrichment36 % in uranium-235. In 2016 reactor conversion to low-enriched uranium fuel (19 ..." | ||
| No 2 (2021) | DEVELOPMENT AND RESEARCH OF ELECTROCATALYTIC SYSTEMS FOR ELECTRODES OF SOLID-OXIDE HYDROGEN-AIR FUEL CELLS | Abstract PDF (Rus) similar documents |
| M. K. Skakov, A. M. Zhilkashinova, S. K. Kabdrakhmanova, M. E. Seitkanova, E. Shaimardan, K. Akatan | ||
| "... electrocatalysts for their use in the electrodes of the membrane-electrode block of a solid-oxide hydrogen-air fuel ..." | ||
| No 3 (2023) | MODELING OF HEAT-STRENGTH INTERACTION OF FUEL AND STRUCTURAL MATERIALS OF AN IRRADIATING DEVICE IN THE ANSYS SOFTWARE | Abstract PDF (Rus) similar documents |
| Y. A. Kabdylkakov, A. S. Suraev | ||
| No 3 (2025) | DEVELOPMENT AND FABRICATION OF A YSZ ELECTROLYTE BY MAGNETRON SPUTTERING FOR INTERMEDIATE-TEMPERATURE SOLID OXIDE FUEL CELLS | Abstract PDF (Rus) similar documents |
| S. Opakhai, K. A. Kuterbekov, K. Zh. Bekmyrza, A. M. Kabyshev, M. M. Kubenova, Zh. S. Zeinulla, N. K. Aidarbekov | ||
| "... oxide fuel cells (IT-SOFCs). The resulting coatings were characterized by scanning electron microscopy ..." | ||
| No 3 (2025) | ANALYSIS OF RADIOACTIVE WASTE AND SPENT NUCLEAR FUEL MANAGEMENT TECHNOLOGIES IN THE CONTEXT OF NUCLEAR POWER DEVELOPMENT | Abstract PDF (Rus) similar documents |
| M. K. Seisenbayeva, V. A. Pospelov, D. I. Abulgazinova, Yu. Yu. Baclanova | ||
| "... The article analyzes the problem of radioactive waste and spent nuclear fuel management ..." | ||
| No 3 (2025) | JUSTIFICATION OF THE SAFE TRANSPORTATION OF SPENT NUCLEAR FUEL FROM THE IVG.1M REACTOR | Abstract PDF (Rus) similar documents |
| G. A. Vityuk, N. Ye. Mukhamedov, V. A. Vityuk, R. A. Irkimbekov, O. M. Zhanbolatov, A. A. Kuzdeubay, A. K. Muhamediev | ||
| "... of Kazakhstan has been working on the issue of the further handling the spent nuclear fuel (SNF) unloaded from ..." | ||
| No 1 (2020) | EVALUATION OF CORROSION CONDITION OF BN-350 REACTOR SPENT FUEL ASSEMBLY CASING MATERIAL AFTER SHORT-TERM THERMAL INFLUENCE | Abstract PDF (Rus) similar documents |
| E. A. Kozhakhmetov, E. T. Koyanbayev, E. D. Dauletkhanov, R. M. Mukhamedzhanova, A. S. Urkunbay, E. E. Sapatayev | ||
| No 2 (2020) | ASSESSEMNT OF BN-350 SPENT NUCLEAR FUEL STATUS IN CONDITIONS OF A LONG-TERM STORAGE | Abstract PDF (Rus) similar documents |
| P. Ye. Krivitsky, Ye. V. Mustafina, I. V. Prozorova, A. A. Prozorov, A. A. Chernov | ||
| "... The article provides outputs of γ-spectrometric survey of containers containing nuclear spent fuel ..." | ||
| No 2 (2025) | THERMAL ANALYSIS FOR THE SPENT FUEL TRANSPORTATION PACKAGE AFTER SHORT-TERM COOLING BY USING COMPUTER SIMULATION MODELING METHODS | Abstract PDF (Eng) similar documents |
| D. B. Zarva, S. A. Mukeneva, Ye. S. Tur, A. V. Gulkin, V. A. Vityuk, E. G. Batyrbekov, A. S. Akayev | ||
| "... for transfer of spent nuclear fuel after the short-term cooling. Spent nuclear fuel source-terms and energy ..." | ||
| No 3 (2018) | VALIDATION OF THE THERMOPHYSICAL MODEL OF IVG.1M REACTOR WCTC-LEU | Abstract PDF (Rus) similar documents |
| A. S. Khazhidinov, D. A. Ganovichev, A. A. Akaev, Ye. A. Martynenko, A. R. Khazhidinova | ||
| "... enrichment fuel (WCTC-LEU) of IVG.1M reactor and experimental data from IVG.1M reactor P17-07, P17-08 and P17 ..." | ||
| No 1 (2019) | STUDYING OF CHANGES IN PHYSICAL AND MECHANICAL PROPERTIES OF MATERIALS OF COMPLETED FA OF THE BN-350 REACTOR UNDER CONDITIONS OF LONGER THERMAL AGING | Abstract PDF (Rus) similar documents |
| Ye. A. Kozhakhmetov, Ye. T. Koyanbaev, Ye. Ye. Sapataev, R. M. Mukhamedzhanova, A. Zh. Beldeubaev | ||
| No 4 (2021) | BARRIERS TO NUCLEAR PROLIFERATION IN THE EXPORT OF THE RUSSIAN FAST REACTORS WITH CLOSED NFC (USING EXAMPLE BREST-OD-300) | Abstract PDF (Rus) similar documents |
| N. V. Gorin, E. V. Kuznetsov, V. P. Kuchinov, A. N. Chebeskov, A. V. Moiseev, V. V. Shidlovskiy, A. V. Krivtsov | ||
| "... In the coming decades, it is possible to start exporting fast reactors with a closed nuclear fuel ..." | ||
| No 4 (2024) | USE OF STABILIZING ADDITIVES FOR TARGETED MODIFICATION AND HARDENING OF Nd2Zr2O7 CERAMICS | Abstract PDF (Rus) similar documents |
| A. L. Kozlovskiy, M. B. Kabiyev, I. E. Kenzhina, A. U. Tolenova | ||
| "... for inert matrices of dispersed nuclear fuel. During the conducted experiments aimed at determining ..." | ||
| No 4 (2024) | THE EFFECTIVENESS OF BIOREMEDIATION OF SOIL CONTAMINATED WITH PETROLEUM PRODUCTS IN THE CONTEXT OF ECO-TOURISM | Abstract PDF (Rus) similar documents |
| G. A. Onerkhan, Ye. B. Badyelgajy, B. A. Kapsalyamov, Z. H. Kystaubayeva, Ye. T. Syzdykov | ||
| No 1 (2018) | DYNAMICS OF CHANGES IN THE KINETIC PARAMETERS OF THE WWR-K RESEARCH REACTOR CORE WITH LOW-ENRICHED FUEL UNDER THE GRADUAL REPLACEMENT OF THE WATER REFLECTOR BY BERYLLIUM REFLECTOR | Abstract PDF (Rus) similar documents |
| D. S. Sairanbayev, S. N. Koltochnik, A. A. Shaimerdenov, D. A. Nakipov, Y. A. Kenzhin | ||
| "... &instrumentation system within the conversion of the reactor WWR-K to low-enrichment fuel. The new reactor core ..." | ||
| No 3 (2018) | IN-PILE TESTS OF WATER-COOLED TECHNOLOGICAL CHANNELS WITH LOW-ENRICHED URANIUM FUEL WITHIN CONVERSION OF IVG.1M RESEARCH REACTOR | Abstract PDF (Rus) similar documents |
| M. K. Skakov, A. D. Vurim, V. S. Gnyrya, A. S. Azimkhanov, A. N. Kolbayenkov, I. K. Derbyshev, Ye. B. Nurzhanov | ||
| No 3 (2019) | EVALUATION OF FISSION PRODUCT REALESE FROM THE FUEL RODS OF EXPERIMENTAL WATER-COOLED TECHNOLOGICAL CHANNELS INTO THE COOLANT OF THE IVG.1M REACTOR | Abstract PDF (Rus) similar documents |
| B. S. Medetbekov, Yu. A. Popov, D. V. Zhmuk | ||
| "... of the fission products (FP) yield from the fuel rods of experimental water-cooled technological channels ..." | ||
| No 4 (2024) | COMPUTATIONAL STUDIES IN SUPPORT OF POSSIBILITY OF CONDUCTING AN IN-PILE EXPERIMENT WITH POWER REACTOR FUEL DURING THE IMPLEMENTATION OF THE LONG-TERM OPERATION MODE OF THE IGR REACTOR | Abstract PDF (Rus) similar documents |
| N. Ye. Mukhamedov, V. A. Vityuk, G. A. Vityuk, A. D. Vurim, R. Ye. Kelsingazina, S. A. Dolzhikov, D. T. Zhengis, A. S. Suraev | ||
| "... Research of prototype fuel elements and fuel assemblies in in-pile tests are an integral part ..." | ||
| No 1 (2025) | STUDY OF THE KINETICS OF STRUCTURAL DAMAGE IN COMPOSITE CER-CER CERAMICS UNDER IRRADIATION WITH HEAVY IONS COMPARABLE TO NUCLEAR FUEL FISSION FRAGMENTS | Abstract PDF (Rus) similar documents |
| Sh. G. Giniyatova, A. L. Kozlovskiy, D. I. Shlimas | ||
| No 3 (2019) | COMPUTATION OF A TEMPERATURE FIELD OF THE IVG.1M WCTC-LEU IN PTIMIZED AND ADVANCED MODELS | Abstract PDF (Rus) similar documents |
| A. S. Khazhidinov, A. S. Akayev, D. A. Ganovichev | ||
| "... A test object is a water-cooled technological channel with low-enriched uranium fuel (WCTC-LEU ..." | ||
| No 4 (2018) | X-RAY STUDIES OF IGR REACTOR GRAPHITE | Abstract PDF (Rus) similar documents |
| O. S. Bukina, I. M. Kukushkin, M. K. Skakov, A. A. Sitnikov, V. I. Yakovlev | ||
| "... The conversion of research reactors to low-enriched uranium (LEU) fuel is assumed on the base ..." | ||
| No 1 (2019) | IN-REACTOR EXPERIMENT FOR THE TESTING OF A FAST-REACTOR PILE IN THE CONTIDIONS OF LOSS-OF-COOLANT ACCIDENT | Abstract PDF (Rus) similar documents |
| N. A. Suleimenov, A. V. Pakhnits, A. S. Suraev | ||
| "... In this paper, the behavior of a model nuclear fuel element of a fast neutron reactor was studied ..." | ||
| No 2 (2020) | PRACTICAL METHODS FOR DETERMINING THE ENERGY PARAMETERS OF REACTOR TESTS IN THE PULSE POWER MODE | Abstract PDF (Rus) similar documents |
| V. A. Vityuk, A. D. Vurim, G. A. Vityuk | ||
| "... and energy release in fuel of fuel rods tested in research reactors. Emphasis is placed on approaches ..." | ||
| No 4 (2019) | MODIFICATION OF TiN COATINGS BY ELECTRON IRRADIATION | Abstract PDF (Eng) similar documents |
| B. Rakhadilov, A. Kenesbekov, R. Kozhanova, L. Zhurerova | ||
| "... coatings under thermal and electron irradiation. Continuous electron irradiation of coated samples ..." | ||
| No 3 (2018) | DEVELOPMENT OF A MODEL FA FOR THE STUDY OF EMERGENCY SITUATION WITH AN IMMEDIATE BLOCKING OF THE COOLANT FLOW IN FAST REACTOR | Abstract PDF (Rus) similar documents |
| V. A. Vityuk, A. D. Vurim, V. M. Kotov, G. A. Vityuk, F. Serre, F. Payot, C. Suteau, L. Trotignon | ||
| "... Possibilities of experimental study of the model fuel assembly (FA) destruction of ASTRID reactor ..." | ||
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