Advertisement

Springer Nature is making SARS-CoV-2 and COVID-19 research free. View research | View latest news | Sign up for updates

Determining the tritium content in the clad of VVÉR-440 fuel rods

This is a preview of subscription content, log in to check access.

Literature Cited

  1. 1.

    V. P. Kruglov, V. M. Ilyasov, I. G. Golubchikova et al., “Tritium content in the water systems of the Novovoronezh Unit 5 reactor,” At. Énerg.,53, No. 4, 225–227 (1982).

  2. 2.

    A. T. Aggeenkov and E. M. Valuev, “Research on the process of removing tritium from irradiated uranium dioxide using an oxidizing treatment in air,”ibid.,45, No. 5, 335–338 (1978).

Download references

Additional information

Voronezh State University. Translated from Atomnaya Énergiya, Vol. 71, No. 3, pp. 259–261, September, 1991.

Rights and permissions

Reprints and Permissions

About this article

Cite this article

Babenko, A.G., Mekhedov, B.N., Popov, S.V. et al. Determining the tritium content in the clad of VVÉR-440 fuel rods. At Energy 71, 773–775 (1991). https://doi.org/10.1007/BF01123802

Download citation

Keywords

  • Tritium
  • Tritium Content