Microstructure and Mechanical Properties of the Fuel Cladding in VVER-1000 after the Thermal Tests That Model Dry Storage Conditions

被引：0
|
作者：
G. P. Kobylyansky
A. V. Obukhov
A. O. Mazaev
E. A. Zvir
P. A. Ilyin
D. E. Markelov
机构：
[1] JSC “SSC RIAR”,
来源：
Russian Metallurgy (Metally) | 2019年 / 2019卷
关键词：
VVER-1000 fuel claddings; strength; plasticity; thermal tests; dry storage; recovery of mechanical properties; annealing of radiation damages;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：421 / 426
页数：5
相关论文
共 21 条
  • [1] Microstructure and Mechanical Properties of the Fuel Cladding in VVER-1000 after the Thermal Tests That Model Dry Storage Conditions
    Kobylyansky, G. P.
    Obukhov, A. V.
    Mazaev, A. O.
    Zvir, E. A.
    Ilyin, P. A.
    Markelov, D. E.
    [J]. RUSSIAN METALLURGY, 2019, 2019 (04): : 421 - 426
  • [2] Impact of Thermal Tests Simulating Dry Storage of VVER-1000 Fuel on the Hydride Phase Morphology in Fuel Element Claddings
    Mazaev A.O.
    Kobylyansky G.P.
    Zvir E.A.
    Shishalova G.V.
    Minduksheva I.A.
    [J]. Inorganic Materials: Applied Research, 2019, 10 (03) : 749 - 756
  • [3] Factors and Mechanisms of Elongation of VVER-1000 Fuel Rods during Thermal Tests Simulating Dry Storage Modes
    Kobylyansky, G. P.
    Mazaev, A. O.
    Zvir, E. A.
    Il'in, P. A.
    Grin, P. I.
    Chertopyatov, E. V.
    Obukhov, A. V.
    [J]. INORGANIC MATERIALS-APPLIED RESEARCH, 2023, 14 (03) : 809 - 817
  • [4] Factors and Mechanisms of Elongation of VVER-1000 Fuel Rods during Thermal Tests Simulating Dry Storage Modes
    G. P. Kobylyansky
    A. O. Mazaev
    E. A. Zvir
    P. A. Il’in
    P. I. Grin’
    E. V. Chertopyatov
    A. V. Obukhov
    [J]. Inorganic Materials: Applied Research, 2023, 14 : 809 - 817
  • [5] Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors
    Alyokhina, S.
    Kostikov, A.
    [J]. KERNTECHNIK, 2014, 79 (06) : 484 - 487
  • [6] RESULTS OF TESTS OF VVER-1000 FUEL ELEMENTS WITH HIGH FUEL BURNUP IN THE MIR REACTOR FOR LOC INCIDENT CONDITIONS
    Alekseev, A. V.
    Goryachev, A. V.
    Izhutov, A. L.
    Dreganov, O. I.
    Kireeva, L. V.
    Kiseleva, I. V.
    Shulimov, V. N.
    [J]. ATOMIC ENERGY, 2018, 123 (03) : 159 - 166
  • [7] Results of Tests of VVER-1000 Fuel Elements with High Fuel Burnup in the MIR Reactor for LOC Incident Conditions
    A. V. Alekseev
    A. V. Goryachev
    A. L. Izhutov
    O. I. Dreganov
    L. V. Kireeva
    I. V. Kiseleva
    V. N. Shulimov
    [J]. Atomic Energy, 2018, 123 : 159 - 166
  • [8] Evolution of microstructure and mechanical properties of VVER-1000 RPV steels under re-irradiation
    Gurovich, B.
    Kuleshova, E.
    Shtrombakh, Ya.
    Fedotova, S.
    Erak, D.
    Zhurko, D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 456 : 373 - 381
  • [9] EXTERNAL RADIATION OF A CONTAINER USED FOR DRY STORAGE OF SPENT VVER-1000 NUCLEAR FUEL FROM THE ZAPOROZHIE NUCLEAR POWER PLANT
    Zalyubovskii, I. I.
    Pismenetskii, S. A.
    Rudychev, V. G.
    Klimov, S. P.
    Luchnaya, A. E.
    Rudychev, E. V.
    [J]. ATOMIC ENERGY, 2011, 109 (06) : 396 - 403
  • [10] External radiation of a container used for dry storage of spent VVER-1000 nuclear fuel from the Zaporozhie nuclear power plant
    I. I. Zalyubovskii
    S. A. Pismenetskii
    V. G. Rudychev
    S. P. Klimov
    A. E. Luchnaya
    E. V. Rudychev
    [J]. Atomic Energy, 2011, 109
123