Atomic Energy

, Volume 117, Issue 3, pp 161–168 | Cite as

Results of Tests of VVER Fuel-Element Cladding Under the Conditions of the First Stage of LOCA

  • D. N. Ignat’ev
  • D. M. Soldatkin
  • A. A. Mokrushin
  • L. P. Loshmanov
  • A. V. Kostyukhina
Article
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A procedure is developed for performing on the PARAMETR stand integrated tests on VVER fuel-element simulators under conditions of the first stage of LOCA. The computational and methodological underpinnings of the experiments make it possible to conduct investigations under pre-determined conditions. The experiments showed the effect of the combinations of temperature-force conditions (factors) of the first stage of the accident on the thermomechanical behavior of fuel-element cladding made of E-110 alloy. The cladding material undergoes a martensite transformation with grain growth. Hardening of the experimental cladding material with a significant reduction of plasticity is noted. The results of the investigations can be used to predict the thermomechanical and corrosion behavior of cladding at the first and second stages of the accident as well as for adjusting the number of depressurized fuel elements in the accident.

Keywords

Fuel Element Fuel Assembly Thermomechanical Behavior PARAMETR Stand Design Basis Accident 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    P. V. Fedotov, O. A. Nechaeva, and V. V. Novikov, “The corrosion behaviour of E-110 sponge based alloy under LOCA conditions VVER-2007,” in: Proc. Int. Top. Meeting of Czech Nuclear Society and European Nuclear Society, Prague, Oct. 2007, pp. 327–331.Google Scholar
  2. 2.
    V. V. Novikov, A. V. Medvedev, and A. V. Salatov, “Substantiation of VVER fuel safety in design basis accidents experimental support,” in: Proc. Int. Meeting on LWR Fuel Performance on Nuclear Fuel: Addressing the Future, Spain (2006), pp. 482–487.Google Scholar
  3. 3.
    G. V. Karetnikov, A. S. Bogdanov, Yu. A. Bezrukov, et al., “Investigation of the behavior of fuel element cladding under the conditions of the initial stage of an accident with a leak in the first loop,” in: 2nd Russ. Conf. Safety Security of NPP with VVER, Podolsk (2001), pp. 30–31.Google Scholar
  4. 4.
    L. P. Loshmanov, P. V. Fedotov, A. V. Salatov, et al., “Modernization of the ID-10 setup for heat-treatment of fuel-element cladding according to the LOCA temperature regime,” in: Physical and Technical Problems of Unconventional Power Engineering and High-Power Pulsed Electrophysics. Physical and Technical Problems of Nuclear Power, MIFI, Moscow (2005), Vol. 8, pp. 172–173.Google Scholar
  5. 5.
    V. P. Spasskov,Yu. G. Dragunov, S. B. Ryzhov, et al., Computational Validation of the Thermohydraulic Characteristics of the VVER Reactor and Reactor Plant, IKTs Akademkniga, Moscow (2004).Google Scholar
  6. 6.
    P. V. Fedotov, A. A. Goncharov, and A. V. Kumachev, “Estimation of water-water energy reactor fuel rod failure in design basis accidents,” in: Proc. of the Water Reactor Fuel Performance Meeting, Kyoto, Oct. 2–6, 2005, pp. 835–837.Google Scholar
  7. 7.
    Yu. Bibilashvili, N. Sokolov, and Salatov, “Experimental researches and modeling of WWER fuel road behaviour in LOCA conditions using RAPTA-5 code,” in: Proc. 3rd Int. Seminar on WWER Fuel Performance Modeling and Experimental Support, Bulgaria, Oct. 4–8, 1999, pp. 221–228.Google Scholar
  8. 8.
    A. V. Nikulina, “Zirconium-niobium alloys for the elements of the cores of pressurized water reactors,” Metalloved. Term. Obrab. Met., No. 8, 7–13 (2003).Google Scholar
  9. 9.
    M. I. Alymov, G. N. Ermolaev, and P. F. Prasolov, “Mechanisms of plastic deformation of textured alloy Zr–1%Nb in the temperature interval 77–550 K,” in: Strength of Materials and Structural Elements of Nuclear Reactors, Energoatomizdat, Moscow (1987), pp. 86–91.Google Scholar
  10. 10.
    Yu. A. Perlovich, M. N. Grekhov, M. G. Isaenkova, et al., “Change of the structure and texture in the volume of cladding tubes made of zirconium-based alloys during ion-plasma surface treatment,” Vopr. At. Nauki Tekhn. Ser. Fiz. Rad. Povr. Rad. Materialoved., No. 3, 59–65 (2004).Google Scholar
  11. 11.
    L. B. Zuev, S. Y. Zavodchikov, and T. M. Poletika, “Phase composition, structure, and plastic deformation localization in Zr–1%Nb alloys,” J. ASTM Int., 3, No. 1, 264–274 (2006).CrossRefGoogle Scholar
  12. 12.
    V. N. Shishov, A. V. Nikulina, and V. A. Markelov, “Influence of neutron irradiation on dislocation structure and phase composition of Zr-base alloys,” in: Proc. 11th Int. Symp. ASTM Zirconium in the Nuclear Industry (1996), pp. 603–622.Google Scholar
  13. 13.
    V. N. Shishov, Regularities and Mechanisms of the Formation of the Microstructure of the Alloys Zr–Nb–(Fe–Sn–O) and Its Evolution under Neutron Irradiation: Dissert. Doct. Techn. Sci., VNIINM (2012).Google Scholar
  14. 14.
    P. V. Fedotov, O. A. Nechaeva, and A. V. Salatov, “Universal model of Zr-alloys plastic straining under VVER design basis accident condition,” in: Proc. 6th Int. Conf. WWER Fuel Performance, Modeling and Experimental Support, Bulgaria, Sept. 19–23, 2005, pp. 529–548.Google Scholar
  15. 15.
    P. V. Fedotov, L. P. Loshmanov, and A. V. Kostyukhin, “Deformation of the alloy E-110 in the α-region,” Deform. Razrush. Mater., No. 2, 29–35 (2013).Google Scholar
  16. 16.
    V. Deniskin, V. Konstantinov, and V. Nalivaev, “Test facility simulation of WWER fuel rods behaviour under initial stage of LB LOCA,” in: Proc. 4th Int. Conf. WWER Fuel Performance, Modeling and Experimental Support, Bulgaria, Sept. 29 – Oct. 3, 2003, pp. 328–332.Google Scholar
  17. 17.
    L. P. Loshmanov, P. V. Fedotov, F. S. Zakharenko, and N. V. Smirnov, “Effect of the temperature regime of the first stage LOCA in VVER type reactors on the mechanical characteristics and deformation behavior of E-110 alloy,” in: Physical and Technical Problems of Unconventional Power Engineering and High-Power Pulsed Electrophysics. Physical and Technical Problems of Nuclear Power, MIFI, Moscow (2005), Vol. 8, pp. 174–175.Google Scholar

Copyright information

© Springer Science+Business Media New York 2014

Authors and Affiliations

  • D. N. Ignat’ev
    • 1
  • D. M. Soldatkin
    • 1
  • A. A. Mokrushin
    • 1
  • L. P. Loshmanov
    • 2
  • A. V. Kostyukhina
    • 2
  1. 1.Luch Research Institute and Scientific Industrial Association (NII NPO Luch)PodolskRussia
  2. 2.National Research Nuclear University MEPhI (Moscow Engineering Physics Institute)MoscowRussia

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