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| Issue |
Title |
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| No 1(121) (2025) |
Features of channel fracture for irradiated austenitic steels. Part 1. Experimental results |
Abstract
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B. Z. Margolin, V. A. Shvetsova, A. A. Sorokin, N. E. Pirogova, A. A. Buchatsky, E. A. Zernov |
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| No 1(121) (2025) |
Features of channel fracture for irradiated austenitic steels. Part 2. Channel fracture model and criterion |
Abstract
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B. Z. Margolin, V. A. Shvetsova, A. A. Sorokin, E. A. Zernov, N. E. Pirogova, A. A. Buchatsky |
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| No 3(119) (2024) |
Estimation of hydrides structure and mechanical properties of irradiated E110 alloy after thermomechanical tests imitating dry storage conditions |
Abstract
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O. O. Zabusov, A. V. Ugryumov, M. M. Grekhov, D. A. Maltsev, A. A. Shishkin, R. A. Kurskiy, A. V. Rozhkov |
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| No 1(117) (2024) |
Radiation and thermal embrittlement of RPV steels: the links of embrittlement mechanisms, fracture modes and microcrack nucleation and propagation properties. Part 1. Strategy, program and methods of experimental and numerical studies |
Abstract
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B. Z. Margolin, V. N. Fomenko, V. A. Shvetsova, E. V. Yurchenko |
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| No 1(117) (2024) |
Radiation and thermal embrittlement of RPV steels: the links of embrittlement mechanisms, fracture modes and microcrack nucleation and propagation. Part 2. Strength and plasticity properties |
Abstract
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B. Z. Margolin, V. N. Fomenko, V. A. Shvetsova, E. V. Yurchenko |
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| No 1(117) (2024) |
Correlation dependences between hardening in terms of yield strength and microhardness for austenitic and ferritic-martensitic steels |
Abstract
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B. Z. Margolin, L. A. Belyaeva, A. A. Sorokin, E. V. Yurchenko, M. N. Grigoriev |
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| No 2(118) (2024) |
Simulation of stainless ferritic-martensitic and austenitic steel hardening after irradiation in ion accelerator. Part 1. Development of a methodology for determining the ion mode irradiation of ferritic-martensitic steels |
Abstract
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B. Z. Margolin, A. A. Sorokin, L. A. Belyaeva |
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| No 2(118) (2024) |
Simulation of stainless ferritic-martensitic and austenitic steel hardening after irradiation in ion accelerator. Part 2. Development of a methodology for determining the ion mode irradiation of austenitic steels |
Abstract
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B. Z. Margolin, A. A. Sorokin, L. A. Belyaeva |
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| No 2(118) (2024) |
Radiation and thermal embrittlement of RPV steels: the links of embrittlement mechanisms, fracture modes and microcrack nucleation and propagation properties. Part 3: Brittle fracture modelling and analysis of the link of microcrack nucleation and propagation properties and embrittlement mechanisms |
Abstract
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B. Z. Margolin, V. N. Fomenko, V. A. Shvetsova, E. V. Yurchenko |
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| No 4(116) (2023) |
On brittle fracture resistance determination of chromium stainless steel irradiated in ion accelerator |
Abstract
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B. Z. Margolin, V. N. Fomenko, F. L. Shishkov, E. V. Yurchenko |
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| No 4(116) (2023) |
Prediction of radiation embrittlement of VVER-1000 RPV welded seam material at lifetime extension up to 60 years and more |
Abstract
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D. Yu. Erak, V. B. Papina, D. A. Zhurko |
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| No 4(116) (2023) |
Study of stress corrosion cracking susceptibility of irradiated ferrite-martensitic stainless steel 07Kh12NMFB in supercritical water. Part 2. Development of corrosion crack identification technique and analysis of autoclave test results |
Abstract
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B. Z. Margolin, N. E. Pirogova, A. A. Sorokin, V. I. Kohonov, A. V. Dub, I. A. Safonov |
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| No 2(114) (2023) |
Structural materials selection for the sodium-cooled reactor plant steam generator |
Abstract
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A. S. Kudriavtsev |
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| No 2(114) (2023) |
Dose dependences for materials of vver pressure vessels and their support structures |
Abstract
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B. Z. Margolin, E. V. Yurchenko |
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| No 2(114) (2023) |
Effects of γ-radiation on fluorite crystals with a trivalent rare-earth ions |
Abstract
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S. E. Sarkisov, V. A. Yusim |
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| No 1(113) (2023) |
Long-term high-temperature exposure effects on mechanical properties and structure of the 42XNM alloy after neutron irradiation in the VVER-1000. Part 1. Mechanical tests |
Abstract
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B. A. Gurovich, A. S. Frolov, E. A. Kuleshova, I. V. Fedotov |
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| No 1(113) (2023) |
Long-term high-temperature exposure effects on mechanical properties and structure of the 42XNM alloy after neutron irradiation in the VVER-1000. Part 2. Structural studies |
Abstract
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B. A. Gurovich, A. S. Frolov, E. A. Kuleshova, D. A. Maltsev, I. V. Fedotov, D. V. Safonov |
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| No 1(113) (2023) |
Study of mechanical properties and brittle fracture resistance for weld metal of WWER RPV |
Abstract
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E. V. Yurchenko, M. N. Timofeev, B. Z. Margolin, S. N. Galyatkin |
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| No 4(112) (2022) |
Effect of sensitization on service properties of welded joints of austenitic pipelines under operation conditions of RP RBMK 1000 |
Abstract
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N. V. Vasiliev, Y. V. Stepanov, M. I. Zueva, P. I. Borkin, E. A. Ivanenko, V. A. Petrov |
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| No 4(112) (2022) |
Radiation-induced structure of austenitic steels with different nickel content under neutron irradiation in SM-3 and BOR-60 reactors |
Abstract
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E. A. Kuleshova, S. V. Fedotov, D. A. Maltsev, A. S. Frolov, D. V. Safonov, N. V. Stepanov, G. M. Zhuchkov, B. Z. Margolin, A. A. Sorokin |
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| No 3(111) (2022) |
Features of the behavior of the dispersion fuel METMET under irradiation |
Abstract
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L. A. Karpyuk, A. M. Savchenko, Yu. V. Konovalov, G. A. Kulakov, S. V. Maranchak, S. A. Ershov, E. V. Maynikov, A. V. Kozlov, A. L. Izhutov, V. Y. Shishin, A. A. Sheldyakov, V. V. Yakovlev |
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| No 2(110) (2022) |
Profile evaluation of the ion irradiation-induced swelling in austenitic stainless steel with varying nickel content |
Abstract
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E. A. Kuleshova, D. A. Maltsev, A. S. Frolov, N. V. Stepanov, B. Z. Margolin, А. A. Sorokin, V. A. Pechenkin, M. V. Bokhovko, U. A. Kobets |
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| No 2(110) (2022) |
Fracture properties and mechanisms for irradiated austenitic steels over high temperature range and formulation of fracture criterion. Part 1. Experimental results |
Abstract
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B. Z. Margolin, A. A. Sorokin, A. A. Buchatsky, V. A. Shvetsova, O. Yu. Prokoshev, N. E. Pirogova |
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| No 2(110) (2022) |
Fracture properties and mechanisms for irradiated austenitic steels over high temperature range and formulation of fracture criterion. Part 2. Fracture criterion and model |
Abstract
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B. Z. Margolin, A. A. Sorokin, A. A. Buchatsky, V. A. Shvetsova, V. N. Fomenko, N. E. Pirogova |
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| No 3(111) (2022) |
Stability of the Y–Ti–O oxides in reactor materials under neutron irradiation at high temperatures |
Abstract
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A. S. Frolov, E. A. Kuleshova, B. A. Gurovich, A. A. Nikitina, D. A. Maltsev, S. V. Fedotova, D. V. Safonov |
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| No 3(111) (2022) |
Corrosion resistance of 12% chrome steel under the operation conditions of a steam generator of a reactor plant with sodium coolant |
Abstract
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A. S. Kudryavtsev, S. A. Suvorov, D. A. Artemieva, R. M. Ramazanov |
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| No 1(109) (2022) |
Investigation of structural-phase transformations in metal of welded joints of reactor plants for nuclear icebreakers |
Abstract
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R. I. Samoylenko, M. N. Timofeev, S. N. Galyatkin, Yu. M. Markova, D. M. Anisimov, S. A. Korolev, S. V. Gurkin |
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| No 1(109) (2022) |
Post-radiation annealing influence on the evolution of the materials properties of the supporting structures of WWER-440 reactor vessels. Part 1: Problem statement and test results |
Abstract
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B. Z. Margolin, E. V. Yurchenko, A. M. Morozov, A. Ya. Varovin |
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| No 1(109) (2022) |
Post-radiation annealing influence on the evolution of the materials properties of the supporting structures of WWER-440 reactor vessels. Part 2: Analysis of the influence of material annealing after low temperature irradiation |
Abstract
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B. Z. Margolin, E. V. Yurchenko, A. M, Morozov, A. Ya. Varovin, S. V. Rogozhkin, A. A. Nikitin |
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| No 1(109) (2022) |
Influence of thermomechanical exposure on the structure of hydrides in irradiated E110 alloy cladding pipes under the conditions of long-term dry storage of spent nuclear fuel |
Abstract
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R. A. Kursky, A. V. Rozhkov, O. O. Zabusov, D. A. Maltsev, M. A. Skundin, A. P. Bandura, E. A. Vasilieva, A. A. Shishkin |
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| No 4(108) (2021) |
Investigation of the microstructure of the base and weld metal of steel Fe–0.08C–18Cr–10Ni–Ti after low-temperature irradiation in the BOR-60 reactor in the range of damage doses from 40 to 101 displacements per atom |
Abstract
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V. S. Neustroev, D. E. Markelov, A. V. Obukhov, B. Z. Margolin, N. E. Pirogova |
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| No 4(108) (2021) |
Study of the metal of the irradiated weld of the WWER-440 reactor body after 45 years of operation |
Abstract
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D. Yu. Erak, A. A. Chernobaeva, K. I. Medvedev, D. A. Zhurko, V. N. Kochkin, M. A. Skundin, S. A. Bubyakin, N. V. Pal, A. A. Reshetnikov |
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| No 4(108) (2021) |
A study of primary damage formation in collision cascades in titanium |
Abstract
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R. E. Voskoboinikov |
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| No 1(105) (2021) |
Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 4. Mechanical properties and fracture mechanisms |
Abstract
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B. Z. Margolin, A. A. Sorokin, V. A. Shvetsova, A. J. Minkin, N. E. Pirogova |
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| No 1(105) (2021) |
Structural integrity assessment and lifetime prediction for the control rods couplings of the WWER-440 reactor. Part 1: Investigation of steel 14Kh17N2 grade embrittlement under neutron irradiation |
Abstract
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A. J. Minkin, B. Z. Margolin, V. N. Fomenko, L. A. Belyaeva, N. E. Pirogova |
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| No 1(105) (2021) |
Structural integrity assessment and lifetime prediction for the control rods couplings of the WWER-440 reactor. Part 2. Assessment of the coupling structural integrity and justification of its material degradation monitoring interval |
Abstract
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A. J. Minkin, B. Z. Margolin, V. G. Fedosov |
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| No 1(105) (2021) |
Structural integrity assessment and lifetime prediction for the control rods couplings of the WWER-440 reactor. Part 3. Optimi- zation of post-irradiation recovery annealing of the control rods couplings |
Abstract
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A. J. Minkin, B. Z. Margolin, L. A. Belyaeva, N. E. Pirogova, A. M. Shumko, S. N. Petrov |
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| No 4(104) (2020) |
Study of nozzles' metal of VVER-440 pressure vessel after 45 years of exploitation |
Abstract
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D. Yu. Erak, K. I. Medvedev, A. A. Chernobaeva, D. A. Zhurko, A. D. Erak, S. A. Bubyakin, A. P. Bandura |
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| No 3(103) (2020) |
Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 1. Research program and cutting out of samples from pressure vessel internals |
Abstract
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B. Z. Margolin, A. Ya. Varovin, A. J. Minkin, D. A. Gurin, V. A. Glukhov |
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| No 3(103) (2020) |
Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 2. Calculated and experimental determination of the fast neutron fluence and damage dose |
Abstract
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N. E. Pirogova, A. D. Dzhalandinov, B. Z. Margolin, R. V. Derkach, A. J. Minkin |
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| No 3(103) (2020) |
Study of changes in the properties of titanium alloys subjected to neutron irradiation |
Abstract
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V. V. Larionov, V. A. Varlachev |
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| No 3(103) (2020) |
Investigation of irradiated metal of WWER-type reactor internals after 45 years of operation. Part 3. Microstructure and phase composition |
Abstract
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E. A. Kuleshova, S. V. Fedotova, B. A. Gurovich, A. S. Frolov, D. A. Maltsev, B. Z. Margolin, A. J. Minkin, A. A. Sorokin |
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| No 2(102) (2020) |
Strength assessment of austenitic steel grain boundaries by impact bending tests for miniature specimens |
Abstract
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B. Z. Margolin, A. M. Morozov, N. E. Pirogova, M. N. Grigoriev |
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| No 2(102) (2020) |
Mechanisms of stress corrosion cracking of irradiated austenitic chromium-nickel steels used for WWER and PWR vessel internals |
Abstract
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B. Z. Margolin, N. E. Pirogova, A. A. Sorokin, V. I. Kokhonov |
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| No 2(102) (2020) |
Evaluation of resistance to corrosion cracking of irradiated austenitic chromium-nickel steels by impact bending tests on miniature specimens |
Abstract
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B. Z. Margolin, N. E. Pirogova, A. A. Sorokin, A. M. Morozov |
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| No 4(100) (2019) |
Calculation of temperature conditions of a plasma sputtering cell for decontamination of nuclear power plant constructions |
Abstract
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A. S. Petrovskaya, S. V. Surov, A. Yu. Kladkov, A. B. Tsyganov |
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| No 4(100) (2019) |
Technology for producing vessel structures of the main circulation pump for BREST reactor |
Abstract
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E. D. Blank, V. A. Guerasimov, M. G. Sharapov, A. N. Vodovozov, A. D. Kashtanov, S. Yu. Shchutsky, A. N. Plakidin |
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| No 4(100) (2019) |
On the experimental lead-cooled installation |
Abstract
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N. V. Aleksandrov, Ye. D. Blank, A. D. Kashtanov, V. V. Stepanov, V. V. Lemekhov, Yu. V. Lemekhov, A. N. Melnikov |
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| No 3(99) (2019) |
Evolution of the structural phase state of E110 fuel claddings under high temperatures and stress |
Abstract
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B. A. Gurovich, A. S. Frolov, E. A. Kuleshova, D. A. Maltsev, D. V. Safonov, V. N. Kochkin, A. A. Reshetnikov |
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| No 2(98) (2019) |
Model of corrosion cracking of irradiated austenitic steels. Part 1. Analysis of damage mechanisms and formulation of the defining |
Abstract
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B. Z. Margolin, A. A. Sorokin, N. E. Pirogova, V. A. Potapova, Aki Toivonen, Faiza Sefta, Cédric Pokor |
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