Cladding rupture life control methods for a power-cycling WWER-1000 nuclear unit

被引:8
|
作者
Pelykh, S. N. [1 ]
Maksimov, M. V. [1 ]
机构
[1] Odessa Natl Polytech Univ, UA-65044 Odessa, Ukraine
关键词
D O I
10.1016/j.nucengdes.2011.05.011
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Using the cladding creep energy theory, taking into account the WWER-1000 fuel assembly four-year operating period transposition algorithm, as well as considering the disposition of control rods, the location of the axial segment limiting the fuel cladding operation time, at day cycle power maneuvering, has been found. It has been shown that the WWER-1000 fuel element cladding rupture life, at normal variable loading operation conditions, can be controlled by an optimal assignment of the coolant temperature regime and the fuel assembly transposition algorithm. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:2956 / 2963
页数:8
相关论文
共 32 条
  • [1] NEW METHODS OF THE WWER-1000 NUCLEAR-POWER PLANT CONSTRUCTION
    TADZER, O
    JADERNA ENERGIE, 1983, 29 (10): : 345 - 347
  • [2] Development of methods for control of xenon oscillations of power distribution in the WWER-1000 rector
    Filimonov, P.E.
    Aver'yanova, S.P.
    Atomnaya Energiya, 1996, 81 (01): : 69 - 70
  • [3] Failure analysis of collector body in WWER-1000 nuclear power plants
    Dashti, H. G.
    Hashemi, B.
    ENGINEERING FAILURE ANALYSIS, 2010, 17 (06) : 1377 - 1388
  • [4] Improvement of the Sewage System for the Nuclear Power Plant WWER-1000 Reactor
    Kondus, Vladyslav
    Pavlenko, Ivan
    Pitel, Jan
    Kulikov, Oleksandr
    Rybalchenko, Volodymyr
    Ivanov, Vitalii
    Ciszak, Olaf
    ADVANCES IN MANUFACTURING IV, VOL 1, MANUFACTURING 2024, 2024, : 279 - 296
  • [5] Determination of the maximum speed of WWER-1000 nuclear reactor control rods
    Khoshahval, Farrokh
    Ahdavi, Abdol Aziz
    ANNALS OF NUCLEAR ENERGY, 2016, 87 : 58 - 68
  • [6] Mathematical modeling of steamgeneator PGV-1000, used in nuclear power plant with WWER-1000 nuclear reactor
    Monev, Vladimir M.
    Filipov, Kalin B.
    PROCEEDINGS OF THE 2021 6TH INTERNATIONAL SYMPOSIUM ON ENVIRONMENT - FRIENDLY ENERGIES AND APPLICATIONS (EFEA 2021), 2021,
  • [7] EFFECT OF OUTPUT HEAT FROM WWER-1000 TYPE NUCLEAR-POWER-PLANTS ON ELECTRICAL AND ENERGETIC EFFICIENCIES OF THE UNIT
    KARAFIAT, J
    KERNENERGIE, 1990, 33 (05): : 210 - 213
  • [8] Features of Temperature Control of Fuel Element Cladding for Pressurized Water Nuclear Reactor "WWER-1000" While Simulating Reactor Accidents
    Zaytsev, P. A.
    Priymak, S. V.
    Usachev, V. B.
    Oleynikov, P. P.
    Soldatkin, D. M.
    TEMPERATURE: ITS MEASUREMENT AND CONTROL IN SCIENCE AND INDUSTRY, VOL 8, 2013, 1552 : 845 - 850
  • [9] Development conception of the control and protection systems of the power reactors of the WWER-1000 type
    Ol'shevskij, Yu.N.
    Zhemchugov, G.A.
    Kutsakov, S.Ya.
    Galkina, T.N.
    Elektrotekhnika, 1999, (06): : 25 - 28
  • [10] OPTIMIZATION OF POWER CONTROL PROGRAM SWITCHING FOR A WWER-1000 UNDER TRANSIENT OPERATING CONDITIONS
    Zhou, Huiyu
    Pelykh, S. N.
    Odrekhovska, I. O.
    Maksymova, O. B.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2018, (01): : 218 - 222