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Corrosion Resistance of Experimental Fuel-Rod Cladding Tested in a Materials Science Research Reactor Under PWR Conditions

  • A. L. Izhutov
  • A. V. Burukin
  • O. N. Vladimirova
  • A. I. DolgovEmail author
  • P. A. Il’in
  • V. V. Kalygin
  • M. A. Mokeichev
  • V. A. Ovchinnikov
Article

Experimental fuel rods were tested in the PV-2 loop facility of the MIR reactor under conditions close to operation of full-size fuel rods in a PWR core. In the tests, the external condition of the cladding of the experimental fuel rods and structural elements of FA was evaluated visually; the thickness of the oxide film on the outer surface of the cladding of some fuel rods was measured. At the completion of the tests, all fuel rods remained tight, and no defects were found on the surface of the cladding and structural elements of FA. The thickness of the oxide film on the surface of the fuel rods made from the alloy E-110 (ultrapure), E-125 did not exceed 10 μm with average fuel burnup 32 MW·days/kg.

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References

  1. 1.
    A. L. Izhutov, A. L. Petelin, A. V. Burukin, et al., “Current and future directions of testing in the MIR reactor,” Trudy AO GNTS NIIAR (2017), Iss. 2, pp. 96–109.Google Scholar
  2. 2.
    O. I. Dreganov, I. V. Kiseleva, V. N. Shulimov, et al., “The results of a computational analysis of the thermomechanical state of VVER-1000 fuel rod after testing in a research reactor channel under loss-of-coolant accident conditions (LOCA),” Vopr. At. Nauki Tekhn. Ser. Fiz. Yad. Reakt., No. 2, 60–66 (2017).Google Scholar
  3. 3.
    A. V. Alekseev, A. V. Goryachev, O. I. Dreganov, et al., “Results of testing in the MIR reactor of VVER-1000 fuel rods with high fuel burnup under loss of coolant accident conditions,” At. Energ., 123, No. 3, 133–137 (2017).Google Scholar
  4. 4.
    A. V. Burukin, A. I. Dolgov, A. L. Izhutov, et al., “Equipment for interim examinations of the MIR reactor storage pool,” in: Proc.10th Int. Conf. on WWER Fuel Performance, Modeling and Experimental Support, Bulgaria, Sept. 7–14, 2013, pp. 244–250.Google Scholar
  5. 5.
    A. V. Burukin, A. I. Dolgov, A. L. Izhutov, et al., “Evaluation of the method of intermediate studies of experimental fuel rods in the holding pool of the MIR reactor,” in: Scientific Annual Report (report on the basic research work performed in 2012), GNTs NIIAR, Dimitrovgrad (2013), pp. 23–26.Google Scholar
  6. 6.
    A. N. Kostyuchenko, “Facility for measuring the thickness of an oxide film on the outer surface of VVER and RBMK fuel rods. New technologies for power engineering, industry and construction,” in: Abstracts and Articles of GNTs RF NIIAR, Dimitrovgrad (2001), Iss. No.4, pp. 38–42.Google Scholar
  7. 7.
    A. Sánchez, N. Doncel, G. Rubio, et al., “Spanish experience of fuel performance under zinc injection conditions in high duty plants,” in: Water Reactor Fuel Performance Meeting, Korea, Oct. 19–23, 2008, p. 8065.Google Scholar
  8. 8.
    A. L. Izhutov, S.V. Romanovskii, V. A. Svistunov, et al., “Improving the technology of maintaining the water chemistry of the loop facilities in the MIR reactor,” in: Problems and Prospects for the Development of Chemical and Radiochemical Monitoring in Atomic Energy Atomenergoanalitika 2014, VVM, St. Petersburg (2014), pp. 277–283.Google Scholar
  9. 9.
    F. Garzarolli and R. Holzer, “Water corrosion of LWR fuel rods, Part 1,” At. Tekhn. za Rubezhom, No. 10, 20–29 (1993).Google Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2019

Authors and Affiliations

  • A. L. Izhutov
    • 1
  • A. V. Burukin
    • 1
  • O. N. Vladimirova
    • 1
  • A. I. Dolgov
    • 1
    Email author
  • P. A. Il’in
    • 1
  • V. V. Kalygin
    • 1
  • M. A. Mokeichev
    • 1
  • V. A. Ovchinnikov
    • 1
  1. 1.State Science Center of the Russian Federation – Research Institute of Atomic Reactors (SSC RIAR)DimitrovgradRussia

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