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Dimensional Stability of the Structural Parts of VVER-1000 FA Made of E-635 Zirconium Alloy

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The dependence of dimensional changes occurring in the structural parts made of E-635 zirconium alloy on the metallurgical and operational factors as a result of thermal creep, radiation growth, and radiation creep was studied. Tests close to operating conditions showed high resistance to radiation growth and thermal and radiation creep of the structural parts of VVER-1000 fuel assemblies made of E-635 zirconium alloy. Parts with greater resistance to creep without irradiation also possess high resistance to creep in the presence of irradiation. However, in-reactor creep can be almost 10 times greater than creep with no irradiation.

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References

  1. V. V. Novikov, M. M. Peregud, A. Yu. Shevyakov, et al., “Experience in using in the VVER-1000 parts made of the alloy E-635,” At. Energ., 115, No. 2, 77–82 (2013).

    Article  Google Scholar 

  2. D. Markov, S. Pavlov, A. Novoselov, et al., “Main results of post-irradiation examinations of new generation fuel assemblies WWER-1000,” in: 8th Int. Conf. on WWER Fuel Performance, Modelling and Experimental Support, Bulgaria (2009), pp. 241–249.

  3. A. S. Zaimovsky, A. V. Nikulina, and N. G. Reshetnikov, Zirconium Alloys in Atomic Energy, Energoatomizdat, Moscow (1994).

    Google Scholar 

  4. A. V. Nikulina, V. A. Markelov, and A. Yu. Gusev, “Zr–1Sn–1Nb–0.5Fe alloy for the piping in RBMK reactors,” Vopr. At. Nauki Tekhn., Ser. Materialoved. Novye Mater., No. 2(36), 58–66 (1990).

  5. A. V. Nikulina, M. M. Peregud, V. F. Kon’kov, et al., Zirconium Alloys Containing Niobium for the Fuel Assemblies of High-Capacity VVER and PWR Reactors Reaching Burnup ≥70 MW·days/kg U: Survey Inform., VNIINM, Moscow (2014).

  6. S. A. Averin, L. P. Sinelnikov, V. L. Panchenko, et al., “Radiation-induced phase changes in zirconium alloys under prolonged irradiation, ”Metalloved. Term. Obrab. Metal., 8, 24–28 (2003).

    Google Scholar 

  7. A. V. Nikulina, V. A. Markelov, M. M. Peregud, et al., “Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores,” in: 11th Int. Symp. Zirconium in the Nuclear Industry, USA (1996), pp. 785–804.

  8. V. N. Shishov, “The evolution of the microstructure of deformation stability and alloys of Zr–Sn–Nb–Fe under irradiation,” Vopr. At. Nauki Tekhn., Ser. Materialoved. Novye Mater., No. 1(72), 90–106 (2012).

  9. G. P. Kobylyansky, A. E. Novoselov, A. V. Obukhov, et al. “Radiation damage of E635 alloy under high dose irradiation in the VVER-1000 and BOR-60 reactors,” in: 16th Int. Symp. Zirconium in the Nuclear Industry, USA (2012), pp. 1–14.

  10. R. Adamson, F. Garzarolli, and C. Patterson, In-Reactor Creep of Zirconium Alloys, ANTI, Sweden (2009).

  11. J. Romero, M. Dahlbäck, and L. Hallstadius, “Mitigating BWR channel distortion: Westinghouse low tin ZIRLO channel,” in: Proc. Int. Top. Meeting TopFuel’13, USA (2013), Vol. 2, pp. 887–891.

  12. R. L. Kesterson, S. J. King, and R. J. Comstock, “Impact of hydrogen on dimensional stability of fuel assemblies,” in: Proc. Int. Top. Meeting on Light Water Reactor Fuel Performance, USA (2000), pp. 795–803.

  13. V. Fidleris, “Reactor affecting in reactor creep of zirconium alloy tubes,” in: Proc. Conf. on Reactor Materials Science, Alushta (1978), Vol. 6, pp. 98–134.

  14. M. I. Solonin, Y. K. Bibilashvili, A. V. Nikulina, et al., “Zirconium alloy for fuel assemblies of new generation WWER-1000,” in: Proc. Int. Top. Meeting TopFuel’99, France (1999), pp. 165–177.

  15. M. M. Peregud, E. G. Afonina, M. N. Sablin, et al., “Creep of alloy E-635 in application to the parts TVSA, FVS-2 and their modifi cations for VVER-1000 reactors,” Tsvet. Metally, 8, 73–76 (2010).

    Google Scholar 

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Authors and Affiliations

  1. Bochvar High-Technology Research Institute for Inorganic Materials (VNIINM), Moscow, Russia

    A. V. Nikulina, M. M. Peregud, E. E. Vorob’ev & T. N. Khokhunova

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  1. A. V. Nikulina
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  2. M. M. Peregud
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  3. E. E. Vorob’ev
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  4. T. N. Khokhunova
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Translated from Atomnaya Énergiya, Vol. 123, No. 4, pp, 196–202, October, 2017.

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Nikulina, A.V., Peregud, M.M., Vorob’ev, E.E. et al. Dimensional Stability of the Structural Parts of VVER-1000 FA Made of E-635 Zirconium Alloy. At Energy 123, 235–243 (2018). https://doi.org/10.1007/s10512-018-0332-6

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  • DOI: https://doi.org/10.1007/s10512-018-0332-6

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