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Procedure for testing VVÉR-1000 fuel in the MIR reactor under the conditions of an accident with ejection of a control rod

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Abstract

A procedure for performing dynamical experiments to study the behavior of VVÉR fuel under the conditions of an anticipated accident with the introduction of positive reactivity has been developed and adopted on the MIR reactor. A power pulse is produced by removing the screen from the absorber in the initial state of the surrounding fuel element. A reactivity compensator, which is moved synchronously with the screen, is provided to decrease the effect on the core. A three-element fragment of a VVÉR-1000 fuel assembly is used as an experimental fuel assembly. The volume of the installed measuring sensors and the rate at which the parameters are recorded are adequate for calculating the thermomechanical state of a fuel element. The precedure developed makes it possible to obtain in an experiment the lineal power density of fuel elements and the pulse parameters that correspond to the computed values for an anticipated accident.

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References

  1. O. Nechaeva, A. Medvedev, V. Novikov, et al., “Researches of WWER fuel rods behavior under RIA accident conditions,” in: Proceedings of the 5th International Conference on WWER Fuel Performance, Modelling, and Experimental Support, Albena, Bulgaria, September 29–October 3, 2003, 2204, pp. 309–318.

  2. A. A. Goncharov, A. V. Kumachev, A. V. Medvedev, et al., “Estimation of the unsealing of VVÉR fuel elements in anticipated accidents,” in: International Scientific-Technical Conference on Ensuring the Safety of Nuclear Power Plants with VVÉR Reactors, Podol’sk, May 23–26, 2005, Section No. 4, Report No. 8.

  3. “Method and apparatus for testing fuel elements in the regime of a reactivity accident in a research reactor operating in a stationary state,” Patent No. 2243605, February 11, 2003; Byull. Izobret. Polez. Modeli, No. 36, 980–981 (2004).

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Authors and Affiliations

  1. State Science Center of the Russian Federation — Research Institute of Nuclear Reactors, Russia

    A. V. Alekseev, I. V. Kiseleva, V. A. Ovchinnikov & V. N. Shulimov

Authors
  1. A. V. Alekseev
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  2. I. V. Kiseleva
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  3. V. A. Ovchinnikov
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  4. V. N. Shulimov
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Translated from Atomnaya Énergiya, Vol. 101, No. 6, pp. 427–431, December, 2006.

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Alekseev, A.V., Kiseleva, I.V., Ovchinnikov, V.A. et al. Procedure for testing VVÉR-1000 fuel in the MIR reactor under the conditions of an accident with ejection of a control rod. At Energy 101, 882–886 (2006). https://doi.org/10.1007/s10512-006-0185-2

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  • DOI: https://doi.org/10.1007/s10512-006-0185-2

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