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
  • [21] Fractography of in-Service Fracture of the Metal in Weld Joint No. 111 of the Steam Generator of a WWER-1000 Power Unit
    A. Ya. Krasovskii
    I. V. Orynyak
    E. E. Gopkalo
    A. V. Bogdan
    I. A. Makovetskaya
    Strength of Materials, 2015, 47 : 670 - 678
  • [22] EFFECT OF OUTPUT HEAT FROM WWER-1000 TYPE NUCLEAR-POWER PLANTS ON EVAPORATION IN COOLING-TOWERS
    KARAFIAT, J
    KERNENERGIE, 1989, 32 (12): : 469 - 470
  • [23] Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor
    Noori-Kalkhoran, Omid
    Yarizadeh-Beneh, Mehdi
    Ahangari, Rohollah
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 612 - 625
  • [24] Investigation of critical safety function "Heat sink" at low power and cold condition for Kozloduy Nuclear Power Plant WWER-1000/V320
    Andreeva, M.
    Pavlova, M. P.
    Groudev, P. P.
    ANNALS OF NUCLEAR ENERGY, 2012, 40 (01) : 221 - 228
  • [25] In-service damage to heat-exchange tubes and welded joints in steam generators of power-generating units of nuclear power plants with WWER-1000
    I. M. Neklyudov
    V. M. Azhazha
    L. S. Ozhigov
    A. S. Mitrofanov
    Strength of Materials, 2008, 40 : 241 - 245
  • [26] IN-SERVICE DAMAGE TO HEAT-EXCHANGE TUBES AND WELDED JOINTS IN STEAM GENERATORS OF POWER-GENERATING UNITS OF NUCLEAR POWER PLANTS WITH WWER-1000
    Neklyudov, I. M.
    Azhazha, V. M.
    Ozhigov, L. S.
    Mitrofanov, A. S.
    STRENGTH OF MATERIALS, 2008, 40 (02) : 241 - 245
  • [27] THEORETICAL ANALYSIS OF STRESS, STRAIN AND FRACTURE FOR FAST-REACTOR FUEL CLADDING UNDER CONSTANT POWER AND POWER-CYCLING CONDITIONS - VISCOELASTIC MODEL OF NUCLEAR FUEL PIN BEHAVIOR
    GITTUS, JH
    NUCLEAR ENGINEERING AND DESIGN, 1974, 28 (02) : 252 - 256
  • [28] Application of the method of initial parameters to analysis of coupled hydromechanical vibrations in piping systems. Part 3. Analysis of forced vibrations in steam piping of WWER-1000 power unit
    I. V. Orynyak
    A. S. Batura
    S. A. Radchenko
    S. M. Ageev
    Strength of Materials, 2012, 44 : 196 - 204
  • [29] Application of the method of initial parameters to analysis of coupled hydromechanical vibrations in piping systems. Part 3. Analysis of forced vibrations in steam piping of WWER-1000 power unit
    Orynyak, I. V.
    Batura, A. S.
    Radchenko, S. A.
    Ageev, S. M.
    STRENGTH OF MATERIALS, 2012, 44 (02) : 196 - 204
  • [30] Effect of the layout of small- and large-series WWER-1000 reactors of nuclear power plants on the stress-strain state of the header-steam generator connector weldment
    Stepanov G.V.
    Kharchenko V.V.
    Babutskii A.I.
    Kobel'skii S.V.
    Orynyak I.V.
    Romanov S.V.
    Trunov N.B.
    Denisov V.V.
    Piminov V.A.
    Strength of Materials, 2007, 39 (5) : 539 - 544